2026-06-06T01:02:13Z https://atomindonesia.brin.go.id/index.php/aij/oai

oai:ojs.aij.batan.go.id:article/963 2021-08-30T07:42:43Z aij:ART

Gamma Radiosynthesis of Colloidal Silver Nanoparticles Stabilized in ι-Carrageenan Under Atmospheric Gases: A Surface Plasmon Resonance Based Study Perkasa, D. P. Yunus, M. Y. Warastuti, Y. Abbas, B. Gamma radiosynthesis; Silver nanoparticles; ι-Carrageenan; Surface plasmon resonance ι-Carrageenan is a biodegradable and biocompatible biomaterial which potentially stabilizes colloidal silver nanoparticles (AgNPs). The present study explored gamma radiosynthesis of AgNPs at varied concentration of ι-carrageenan solutions. The reaction system contained 1.0 mM silver precursor from silver nitrate salt. Gamma irradiation was conducted at doses up to 20 kGy under simple condition, i.e., atmospheric gases and without addition of hydroxyl radical scavenger. The behavior of AgNPs in suspension was characterized based on their surface plasmon resonance (SPR) absorption spectra which were measured using UV-vis spectrophotometer. The results show that colloidal AgNPs were successfully radiosynthesized due to dual stabilizing/reducing activity of ι-carrageenan. The degradation product of ι-carrageenan shows antioxidant activities, which increase the reducing condition of the  reaction system. TEM micrograph reveals that the nanoparticles are spheroid in shape and monodisperse with an average particle size of below 10 nm. The SPR spectra indicate that the highest AgNPs concentration is found for irradiation at a dose of 10 kGy and ι-carrageenan concentration of 1.0 % (w/v). However, instability of AgNPs occurred a day after radiosynthesis due to oxidative dissolution and agglomeration. Further works on pH adjustment and optimization on irradiation dose and ι-carrageenan concentration are critical to improve the stability of colloidal AgNPs. National Research and Innovation Agency National Nuclear Energy Agency 2021-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/963 10.17146/aij.2021.963 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 111-119 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/963/981 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1476 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1493 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1492 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1575 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1576 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1766 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1817 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/1818 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/2039 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/2040 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/2041 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/2042 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/963/2043 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1414 2024-12-03T02:00:49Z aij:ART

The Modelling and Analysis of iPWR-Type SMR Core Dynamics: Control Rods, Reactivity Feedback, and Thermal-Hydraulic Effects Septawijaya, G. Sukarman, S. Bakhri, S. Subekti, M. Neutronic; Thermal hydraulic; Small Modular Reactor core Development plans for Nuclear Power Plants (NPPs) in Indonesia have been widely discussed. One of the planned NPP types is the Small Modular Reactor (SMR). Human resource readiness is an essential aspect to be considered before constructing an NPP. Simulators capable of illustrating core dynamics can be used to educate the public about the processes within a nuclear reactor. Core modeling is a key component in developing an NPP simulator. The neutronic behavior of the reactor core is modeled using point kinetics equations, while the thermal-hydraulic aspect uses Mann’s model. The results indicate that the modeled core can operate up to 160 MWt and other operating parameters at maximum power align well with the SMR reactor design certification data. National Research and Innovation Agency National Research and Innovation Agency 2024-11-18 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1414 10.55981/aij.2024.1414 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 239-248 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1414/1138 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1414/2546 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1414/2547 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1414/2548 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1414/2549 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1414/2560 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1239 2022-04-13T13:05:11Z aij:PRVv48no1

Preface Atom Indonesia Vol 48 No 1 preface48no1, preface48no1 National Research and Innovation Agency 2022-03-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1239 10.17146/aij.2022.1239 Atom Indonesia; Vol 48, No 1 (2022): April 2022 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1239/1015 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1769 2025-08-07T00:44:56Z aij:CVRv51no2

Cover Atom Indonesia Vol 51 No 2 indonesia, atom National Research and Innovation Agency 2025-04-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1769 10.55981/aij.2025.1769 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1769/1181 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1203 2023-06-03T02:55:28Z aij:ART

Dose Evaluation of Head and Neck Cancer IMRT Treatment Planning Based on Gamma Index Analysis of Varian Halcyon 2.0 Linac Purwati, W. Suhaimi, F. Wibowo, W. E. Pawiro, S. A. Halcyon 2.0; Head and neck cancer; Gamma index analysis; EPID-portal dosimetry Varian Halcyon 2.0 linear accelerator was launched and became available for clinical use in 2018. Therefore, it is necessary to evaluate the accuracy of exit fluence of the Halcyon 2.0 for quality assurance (QA) of head and neck cancer treatment planning, pretreatment, and treatment. The accuracy of the exit fluence for twenty treatment plannings has been evaluated by conducting gamma analysis for QA pretreatment and treatment in each field and composite field by using criteria for gamma index 3 %/3 mm and 2 %/2 mm. The QA pretreatment results are in the average value for each criterion for each field and composite fields on actual gantry angle and null gantry angle with gamma passing rate (GPR) of over 99 % (range 99.78 %-99.95 %) The total treatments consisted of 2717 fractions. The analysis results of GPR for fields were 99.32 % and 97.74 % for gamma indexes of 3 %/3 mm and 2 %/2 mm, respectively. In addition, the analysis results of GPR for composites were 95.46 % and 81.38 % for gamma indexes of 3 %/3 mm and 2 %/2 mm, respectively. Based on this result, the average GPRs of QA pretreatment are ≈ 99 % of the total pixels. This means the prediction dose of Varian Halcyon 2.0 is accurate. The average GPRs of treatment is nearly  90 %, showing that Varian Halcyon 2.0 is effective for creating treatment plans for complex cases. National Research and Innovation Agency Universitas Indonesia 2023-03-29 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1203 10.55981/aij.2023.1203 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 27-32 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1203/1063 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1203/2244 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1203/2245 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1203/2246 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1203/2247 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1203/2248 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1090 2020-08-31T11:48:51Z aij:CVRv46no2

Cover Atom Indonesia Vol 46 No 2 cover, cover National Research and Innovation Agency 2020-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1090 10.17146/aij.2020.1090 Atom Indonesia; Vol 46, No 2 (2020): August 2020 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1090/847 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1403 2023-12-19T04:16:24Z aij:CVRv49no3

Cover Atom Indonesia Vol 49 No 3 cover49no3, cover49no3 Rohandi National Research and Innovation Agency 2023-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1403 10.55981/aij.2023.1403 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1403/1101 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1055 2021-06-28T15:53:36Z aij:ART

Proposed Managements of 137Cs Contaminated Soil: Case Study in South Tangerang City Setiawan, B. Iskandar, D. Nurliati, G. Sriwahyuni, H. Mirawaty, M Artiani, P. A. Heriyanto, K. Ekaningrum, N. E. Purwanto, Y. Sumarbagiono, S Contaminated soil; 137Cs; Decontamination; Management of contaminated soil; Treatments Recently, BAPETEN found contamination of 137Cs while testing environmental radiation monitoring equipment in an area in South Tangerang City. The area, therefore, needs to be cleaned up by performing decontamination followed by the activity of treating the contaminated soil. The decontamination works were carried out by excavating the contaminated soil on the surface to a depth of more than 1.5 m, and then the soils were put into the 100L drum. Decontamination work resulted in a significant reduction dose exposure in the area to 0.3-0.75 mSv/h. The drums containing contaminated soil were then sent to the interim storage facility in BATAN Serpong facility for further treatment. To resolve the 137Cs contaminant, some alternatives in the decontamination and management of the contaminated soils were studied. Some techniques and strategies for decontamination and managing 137Cs are presented in this paper. Management that involves wet and dry methods will be proposed in this paper. By comparing and evaluating various alternative management methods, an appropriate method for treating the contaminated soil in South Tangerang City can be obtained. The objective of the study was to find a suitable management method for the contaminated soil based on the proposed alternative management methods.In the present case, the compaction method seems promising for use soon. National Research and Innovation Agency 2021-04-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1055 10.17146/aij.2021.1055 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 65-76 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1055/899 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1819 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1970 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1973 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1981 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1982 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/1983 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/2001 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1055/2002 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1392 2024-09-10T08:58:51Z aij:ART

Bibliometric Analysis of the Literature on Carbon Ion Therapy Using VOSviewer Software and Dimensions Database El Bekkouri, H. Al Ibrahmi, E. El-Asery, M. Bardane, A. Didi, A. El Mahjoub, C. Sadoune, Z. Carbon ion therapy; VOSviewer; Dimensions database; Bibliometric analysis This study aims to carry out a bibliometric assessment of the worldwide research literature and historical research results on carbon ion therapy for cancer treatment. To carry out this work, we used the VOSviewer software and the Dimensions database. The VOSviewer software tool examined 2,500 publications exported from the Dimensions database. The results show a notable upward trajectory in academic research on carbon ion therapy since 1994, with 2020 showing the highest volume of publications. “Biomedical and Clinical Sciences”, “Physical Sciences”, “Oncology and Carcinogenesis”, and “Medical and Biological Physics” are the most important research categories. “Physics in Medicine and Biology” and “Medical Physics” are the leading journals for research publications on carbon ion therapy. Scrutiny based on term occurrences demonstrates the shift in research interest towards carbon ion radiation therapy. The analysis of bibliographic couplings concerning different countries revealed that Japan is the most dynamic and prolific country based on the number of publications (659) and citations (13734), followed by Germany with 590 publications and 19679 citations. These analytical studies provide a thorough overview of academic publications dedicated to using carbon ions for tumor treatment. This data is anticipated to be highly valuable for researchers seeking to pinpoint the most recent developments and emerging trends in this field of research. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1392 10.55981/aij.2024.1392 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 183-189 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1392/1125 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1392/2461 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1392/2462 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1392/2463 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1392/2464 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1392/2474 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1154 2022-04-12T07:34:33Z aij:ART

The Evaluation of Fission Barrier Height by Fission Toy Model Approach Kurniadi, R. Suud, Z. Perkasa, Y. S. Fission barrier; Fission Toy Model; Stochastic principle Fission yields are compulsory data on the development of nuclear technology. Therefore, it is necessary to provide complete data. However, the expected experimental data encompass only a tiny fraction of various nuclides; not even all nuclides have fission product data. JENDL and ENDF are databases that have completed the experimental data. These databases were obtained through the process of evaluating experimental data. The evaluation technique used includes the results of theoretical research that has been carried out. Fission Toy Model (FTM) is a fission model proposed to complement the preexisting ones. Each model has advantages and disadvantages. The advantage of the FTM model is that it uses stochastic principle in its calculations.This research aims to obtain a fission barrier through the FTM. The work is related to calculating the fission barrier using the random nature of nucleon position. The calculation technique is basically to take advantage of the random nature of the nucleon position to calculate the Coulomb energy. Then, by calculating several essential points, a data set was obtained that can be used to produce a curve that relates the Coulomb energy to the mass number and the atomic number of a nuclide.The success of this research is indicated by the calculation results that are close to the experimental value compared to other methods. National Research and Innovation Agency 2022-03-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1154 10.17146/aij.2022.1154 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 15-19 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1154/1009 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1154/2133 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1154/2134 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1154/2135 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1154/2136 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1472 2025-08-07T00:44:56Z aij:ART

Atmospheric Plasma-Assisted Preparation of Graphene Oxide from Biomass: Characterization and Elemental Analysis Handayani, A. H. Amalia, F. Noviantana, E. V. Mulyaningsih, T. R. Waris, A. Dimyati, A. Graphene oxide; Atmospheric Plasma; NAA; SEM-EDS; Biomass; Raman spectroscopy Graphene oxide (GO) was successfully synthesized using the atmospheric plasma process with biomass precursors, including coconut fronds, palm fronds, and rambutan stems, within a five-minute processing time. Plasma technology converts near-waste materials into valuable resources with potential for various applications. Graphene oxide, in particular, exhibits high mechanical strength, excellent electrical conductivity, good biocompatibility, and a large surface area, making it a highly versatile material. Raman spectroscopy was used to analyze the formation of synthesized graphene. The presence of organic and inorganic elements in graphene oxide was characterized using a scanning electron microscope equipped with energy-dispersive X-ray spectroscopy (SEM-EDS) and neutron activation analysis (NAA). SEM-EDS analysis revealed that the C:O ratio in plasma-derived graphene oxide exceeded 80 % in each sample. NAA identified 22 inorganic elements, which are naturally present in biomass. Understanding the elemental composition of plasma-synthesized graphene oxide is essential for evaluating its potential applications and identifying necessary purification steps. The oxygen content in the synthesized material, which primarily originates from the inherent properties of biomass, can be regulated by optimizing plasma parameters. Using biomass precursors makes plasma-synthesized graphene oxide an economically viable option for large-scale production. National Research and Innovation Agency The authors would like to thank Nuclear Power Research Organization (ORTN) for its financial support. The authors acknowledge the facilities, scientific and technical support from Neutron Scattering Laboratory and Research Nuclear Reactor G. A. Siwabessy, 2025-04-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1472 10.55981/aij.2025.1472 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 89-96 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1472/1165 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1472/2441 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1472/2671 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1472/2672 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1472/2673 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1472/2674 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1147 2022-12-22T17:40:30Z aij:ART

The Investigation of Lead Borate Glass Composites for Boron Neutron Capture Therapy Shielding Ali, M. S. Abdelmonem, A. M. Elshamndy, S. K. Shoraiet, G. M. Mustafa, T. M. Hassan, G. S. BNCT; Thermal neutron shielding; Gamma-ray shielding; Lead borate glass; Monte carlo simulation In this work, we studied the lead borate glass composites to optimize its shielding properties of thermal neutrons and gamma-rays for Boron Neutron Capture Therapy (BNCT) applications. Attenuation coefficients, half-value layer (HVL), and tenth-value layer (TVL) were measured for a broad range of gamma-ray energies, i.e., 356, 511, 662, 1173, 1274, and 1332 keV experimentally. Theoretical results using XCOM software show an agreement with the NaI(Tl) detector-based experimental measurements. The attenuation of collimated thermal neutrons, from Cf-252 source, was simulated using Monte Carlo-based code and compared experimentally with measurements by BF3 detector. A reasonable agreement between simulations and experiments was observed, suggesting that the shielding properties of lead borate glass (LBG) composites are monotonically increasing with the increasing of the lead and boron additives. National Research and Innovation Agency Reactor Physics Department, Nuclear Research Center, Atomic Energy Authority, Cairo, Egypt. 2022-12-21 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1147 10.17146/aij.2022.1147 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 237-246 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1147/1051 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2015 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2016 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2017 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2206 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2207 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2208 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2209 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1147/2214 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1763 2026-04-09T08:48:40Z aij:ART

Monte Carlo Simulation of Pediatric Chest Radiography: Validation of the Irradose Through Comparison with MCNP El Basraoui, O. Qassimi, O. Kabach, O. Messous, M. Y. Tahiri, N. Arianto, F. El Bounagui, O. Absorbed dose; Monte Carlo simulation; MCNP code; Biological tissues; HCNO; Cylindrical phantom Radiological examinations are essential for medical diagnostics, but accurate estimation of dose deposition is crucial for patient safety, particularly in pediatric patients. This study employs Monte Carlo simulations with the MCNP code and a newly developed custom program, Irradose, to analyze photon dose deposition in a cylindrical phantom representing the thorax of a 10-year-old child. Two tissue-equivalent compositions were modeled: water and a more realistic HCNO-based soft tissue mixture. Depth-dose distributions obtained with Irradose were compared to MCNP results. Both codes predicted a maximum dose at 2 cm depth, followed by exponential fall-off, with deviations remaining below 5% across the depth range. These results validate Irradose as a reliable and computationally efficient tool for pediatric chest dosimetry in phantom studies. While limited to simplified geometries, this work demonstrates the potential of Irradose for use in preliminary dose assessments and as a complement to established Monte Carlo codes. National Research and Innovation Agency no funding 2026-03-31 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1763 10.55981/aij.2026.1763 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 63-71 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1763/1208 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1763/2927 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1763/2928 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1763/2929 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1763/2930 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1763/2931 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/757 2022-02-12T05:46:00Z aij:ART

Thermal Hydraulic Modeling of Once-Through Steam Generator by Two-Fluid U-Tube Steam Generator Code Zeighami, A. Rahgoshay, M. Khaleghi, M. Hashemi-Tilehnoee, M. THERMIT; OTSG; Steam generator; PWR The THERMIT U-tube steam generator (THERMIT-UTSG) code was used for evaluation for the parametric study of a scaled once-through pressurized water reactor steam generator (OTSG) made by Babcock Wilcox. The results of the code were compared to the experimental data of the 19-tube OTSG and a simple heat transfer code that was developed by Osakabe. The main calculated thermodynamic parameters were primary-secondary fluid temperatures, tube wall internal and external temperatures that were subjected to primary and the secondary fluid, and the secondary fluid vapor quality. The assessed code can be used for modeling the OTSGs with some modification. The results of THERMIT-UTSG were in agreement with the experimental results and the prediction of Osakabe’s numerical model. National Research and Innovation Agency THERMIT OTSG Steam generator PWR 2017-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/757 10.17146/aij.2017.757 Atom Indonesia; Vol 43, No 3 (2017): December 2017; 145-148 2356-5322 0126-1568 10.55981/aij.v43i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/757/548 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/757/705 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/757/703 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/757/704 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/757/707 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/757/706 Copyright (c) 2017 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1275 2023-12-19T03:11:18Z aij:ART

Neural Network Predictions of Atomic Form Factors and Incoherent Scattering Functions Mohammedi, B. Benkharfia, H. Beladel, B. Mellel, N. Bessine, K. Moulai, N. Artificial neural networks; Atomic form factors; Incoherent scattering function; Compton total scattering cross sections. In order to predict atomic form factors and incoherent scattering functions which are used to calculate the coherent and incoherent total scattering cross sections, a technique based on artificial neural networks of the multilayer type was implemented. In this context, two neural models have been developed and compared with those in the literature. This study revealed both the accuracy of the results obtained and the effectiveness of the designed model. The mean relative error for the least estimated property does not exceed 16.5 %. The software realized in this way give a prediction of the above parameters for the input variables Z: Atomic number, x: sin(ϑ/2)/λ and E: Photon energy, and it provides users with flexibility for prediction. The advantages of this technique lie in its very fast handling, due to its ease of use, and in the two integrated networks, which it guarantees for a variety of input parameters such as atomic number, photon energy, and momentum transfer variable. National Research and Innovation Agency Nuclear Research Center of Birine, Algeria CRNB 2023-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1275 10.55981/aij.2023.1275 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 151-158 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1275/1091 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1275/2165 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1449 2024-04-05T11:14:03Z aij:PRVv50no1

Preface Atom Indonesia Vol 50 No 1 Yusuf, Anggiana Rohandi National Research and Innovation Agency 2024-02-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1449 10.55981/aij.2024.1449 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1449/1116 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1102 2021-12-09T05:39:37Z aij:ART

The Dose Distribution from Iridium-192 Source on Cervical Cancer Brachytherapy by Manchester System Using Monte Carlo Simulation Kurniati, F. Krisna, F. P. Junios, J. Haryanto, F. Brachytherapy; CT image; Ir-192 source; Manchester system; Monte carlo simulation One treatment for cervical cancer is to use radioactive sources that directly target the cancer cell called brachytherapy. This study is aimed to determine dose distribution at phantom pelvis using the DOSXYZnrc Monte Carlo code. The phantom was derived from a CT scan image of the DICOM-type pelvis with a size of 50 × 50 × 28.8 cm obtained from Santosa Kopo Hospital. The source used was Ir-192, which makes an asymmetrical beam with a size of 0.45 × 0.09 × 0.09 cm. Monte Carlo simulation was performed to determine the dose distribution of the Ir-192 source on cervical cancer CT images based on the Manchester system. The Monte Carlo simulation was divided into two models with distance variations on the applicator. Model A used TPS data with a distance between sources of 0.9 cm, while model B had a distance between sources of 0.5 cm. The distribution of dose resulting from the Monte Carlo simulation was analyzed and compared with TPS data. The results showed that at the range of 50 %, dose distribution in model A reaches the end of 3.9 cm. When compared to the range of 50 % dose distribution at the TPS results that reaches the point of 4 cm, it produces a deviation value of 2.5 %, which is still within the tolerance range. Model A and Model B provide different dose distribution. In model B, it reaches 3.86 cm, resulting in a deviation of 1.02 %, which is still within the tolerance range. The resulting γ-index value for the 50 % dose distribution was 2.26, while the whole area's GPR value was 94.13 %. This indicates a difference in dose distribution between the two models. Therefore, the smaller the distance between the sources, the shorter the dose distribution range with relatively more uniform dose distribution.  National Research and Innovation Agency This study was fully supported by Program Penelitian Kolaborasi Indonesia (PPKI) (grant number 020/WCU-ITB/LL/I/2020) 2021-12-03 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1102 10.17146/aij.2021.1102 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 205-211 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1102/996 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1102/1908 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1102/2077 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1102/2078 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1102/2079 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1102/2080 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1466 2025-04-14T03:30:31Z aij:ART

Brain Tumor Segmentation on MR and CT Images Using Fuzzy C-Means and Active Contour Methods Hamid, M. Mu'ti, A. Intifadhah, S. H. Putri, E. R. Active contour; Brain tumor; Fuzzy C-Means; Segmentation A brain tumor is a dangerous brain disease that can attack anyone. It can be described as the abnormal growth of cells in or around the brain, leading to impaired brain function. The first step in diagnosing a brain tumor is to perform an MRI (Magnetic Resonance Imaging) scan. The research aims to analyze the segmentation results of brain tumor MRI and CT (Computed Tomography) images using the Fuzzy C-Means and Active Contour methods. The evaluation is based on ROC parameters, including accuracy, dice score, precision, and sensitivity. The methodology involves analyzing data from secondary image sources, using MATLAB for the segmentation process, and evaluating the results of image segmentation by radiologists. Four ROC measurements were used for each method. The segmentation evaluation results for MRI images show that the Fuzzy C-Means method achieved a precision of 0.92; sensitivity of 0.64; dice score of 0.76; and accuracy of 0.61. The Active Contour method, on the other hand, obtained a precision of 0.97; a sensitivity of 0.99; a dice score of 0.98; and an accuracy of 0.96. For CT images, the Fuzzy C-Means method yielded a precision of 0.72; sensitivity of 0.98; dice score of 0.83; and accuracy of 0.71. The Active Contour method obtained a precision of 0.96; a sensitivity of 0.95; a dice score of 0.96; and an accuracy of 0.92. These results indicate that the Active Contour method, especially with MRI images, provides better segmentation performance. In conclusion, the segmentation results from the Active Contour method can be used as additional information for doctors in diagnosing the presence of tumors. National Research and Innovation Agency 2025-03-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1466 10.55981/aij.2025.1466 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 43-49 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1466/1154 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1466/2640 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1466/2643 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1466/2644 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1466/2645 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1271 2022-08-24T16:08:57Z aij:ACKv48no2

Acknowledgement Atom Indonesia Vol 48 No 2 ack48no2, ack48no2 National Research and Innovation Agency 2022-07-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1271 10.17146/aij.2022.1271 Atom Indonesia; Vol 48, No 2 (2022): August 2022 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1271/1032 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1874 2026-02-26T03:01:50Z aij:CVRv51no3

Cover Atom Indonesia Vol 51 No 3 indonesia, atom National Research and Innovation Agency 2025-08-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1874 10.55981/aij.2025.1874 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1874/1198 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1321 2023-04-27T03:24:05Z aij:PRVv49no1

oai:ojs.aij.batan.go.id:article/1268 2023-08-29T02:15:31Z aij:ART

Assessment of 137Cs in the Environment of Hetauda City, Nepal by In-Situ Gamma Ray Spectrometry Mishra, A. Khanal, R. Cesium; Gamma ray spectrometry; Surface activity; Annual effective dose A significant amount of 137Cs radioactive fallout have been spread in the atmosphere due to nuclear weapon testing and nuclear reactor disasters. This fallout eventually settles on the Earth's surface, and because 137Cs has a long half-life, it remains in the environment for an extended period. Mapping the distribution of 137Cs is crucial, and this study aims to assess the radioactive deposition of 137Cs in the ground to establish baseline data for its distribution in the environment of Hetauda City, Nepal. Recently, Hetauda City has been designated as the capital city of the Bagmati province. To measure 137Cs deposition, portable (backpack) gamma ray spectrometer was used with a 0.347-liter NaI(Tl) detector.  Rapid measurement was carried out while walking at a pace of less than 2 km/h, and the distance between the detector and the ground was maintained at less than 1 m with the detector pointing downward. The surface activity of 137Cs was measured in the range of 0.003 to 2.382 kBq/m2, with an average value of 0.581 ± 0.343 kBq/m2. The spatial variability of 137Cs was found to be smooth in the area, and the mean annual effective dose calculated was 0.379 ± 0.224 µSv. The low dose rates and smooth spatial distribution of 137Cs in the environment indicate no contamination, and the trace amount present could be due to global fallout from weapons testing and nuclear accidents. The results were compared with previously reported values worldwide. National Research and Innovation Agency 2023-08-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1268 10.55981/aij.2023.1268 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 109-113 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1268/1081 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1268/2298 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1268/2301 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1268/2306 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1268/2307 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1268/2308 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1030 2021-06-28T15:53:36Z aij:ART

Radon Concentrations in Canned Liquid Juice Abojassim, A. A. Ionization radiation; Alpha particles; 222Rn concentrations; Canned liquid juice This study was performed at University of  Kufa, Iraq, using canned liquid juice samples found in Iraqi markets due to the absence of environmental contamination from radionuclides emitting 222Rn concentrations using RAD-7 detectors. The annual effective dose (AED) of 222Rn was estimated for children and adults from the ingestion of canned liquid juice samples. The estimated concentrations of 222Rn in unit (mBq/L) ranged from 35.4 to 249.1, with an average of  77.880.24 ± 15.42. It also shows that the AED values for children and adults in (nSv/y) ranged from 19.11 to 134.48 with an average of 43.31 ± 8.32 and from 22.67 to 159.55 with an average of 51.39 ± 9.88, respectively. All estimated results of 222Rn concentrations for juice samples were lower than the natural limits provided by the WHO and the European Union Commission to the public (0.5 and  1 Bq/L, respectively). Therefore, there are no health hazards from drinking juice sold in Iraq markets. National Research and Innovation Agency 2021-04-04 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1030 10.17146/aij.2020.1030 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 1-4 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1030/884 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1030/1710 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1030/1951 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1030/1952 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1030/1953 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1030/1978 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1175 2021-08-30T07:42:43Z aij:CVRv47no2

Cover Atom Indonesia Vol 47 No 2 cover472, cover472 National Research and Innovation Agency 2021-06-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1175 10.17146/aij.2021.1175 Atom Indonesia; Vol 47, No 2 (2021): August 2021 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1175/973 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1483 2024-12-20T09:51:09Z aij:ART

Radiation Dose Prediction for Cervical Cancer Patients Using IMRT Technique with a Machine Learning Model Based on Support Vector Regression (SVR) Mushaddaq, R. F. Sihono, D. S. K. Prajitno, P. Cervical cancer; Support Vector Regression (SVR); Radiotherapy planning; Machine learning; Intensity Modulated Radiation Therapy (IMRT) Cervical cancer poses significant global health challenges, necessitating the need for innovative treatment approaches. This study addresses the gap in current radiotherapy methods by integrating Support Vector Regression (SVR) to predict radiation doses for cervical cancer treatment, thereby enhancing the precision of Intensity Modulated Radiation Therapy (IMRT). Using datasets from 102 and 173 cervical cancer cases, we developed and validated an SVR model to predict dose distributions based on radiomic and dosiomic features. The model demonstrated strong performance, achieving a Mean Absolute Error (MAE) of 0.069 for the testing data, with specific performance metrics as follows: bladder mean dose MAE of 0.0693, bowel mean dose MAE of 0.0926, and rectum mean dose MAE of 0.0779. These findings highlight the potential of machine learning to refine radiotherapy planning, reduce the workload on medical physicists, and improve patient outcomes. Future research should focus on expanding dataset sizes and enhancing model precision, particularly for anatomically challenging regions. National Research and Innovation Agency 2024-11-25 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1483 10.55981/aij.2024.1483 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 281-288 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1483/1144 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2591 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2592 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2593 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2594 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2595 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2596 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1483/2597 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1171 2022-08-22T00:27:11Z aij:ART

Effect of Starch and Chitosan Addition on Swelling Properties of Neutralized Poly(Acrylic Acid)-Based Superabsorbent Hydrogels Prepared by Using γ-Irradiation Technique Barleany, D. R. Heriyanto, H. Alwan, H. Kurniawati, V. Muyassaroh, A. Erizal, E Acrylic acid; Starch; Chitosan; Radiation; Superabsorbent Superabsorbent hydrogels are polymers with a 3D network that have attracted the attention of scientists and industrialists because of their fantastic ability to absorb and retain water and aqueous solutions. The most widely used and commercially available superabsorbent hydrogels are synthetic K-acrylate materials. In this novel study, superabsorbent hydrogels have been developed using natural ingredients to have more biodegradable properties. Superabsorbent hydrogels were synthesized from acrylic acid, cassava starch, and chitosan using the γ-irradiation method under different experimental conditions. The γ-irradiation technique was chosen to produce hydrogels free of residues that may remain when chemical crosslinkers are used. The effects of irradiation dose, acrylic acid composition, and the amount of cassava starch and chitosan on the characteristics of produced hydrogels were analyzed. The resulting polymers were further characterized by fourier transform infrared spectroscopy (FTIR) and scanning electron microscope (SEM) to evaluate the structure. The thermal behavior of superabsorbent products at different neutralization doses was tested with differential scanning calorimetry (DSC). FTIR data indicated that the grafting reaction was successfully implemented in this work. SEM analysis showed that the hydrogel produced from this study was porous and there was a reduction in pore size with the addition of starch and chitosan. It can be concluded that the addition of cassava starch and chitosan affects the acrylic acid-based superabsorbent properties, which are pore size, thermal behavior, gel content, antibacterial activity, and swelling capacity in water, salt, and urea solutions. The best hydrogel was obtained by adding 0.25 g of cassava starch and 0.25 g of chitosan, using 50 % acrylic acid neutralization and 5 kGy γ-irradiation doses. The graft polymers possess the maximum swelling capacity of 670 g/g for distilled water, 520 g/g for NaCl solution, and 767 g/g for urea solution (relative to the dry weight). These products were sterile from Escherichia coli bacteria and had the potential to be applied as superabsorbent resins for various fields. National Research and Innovation Agency Center for Application of Isotopes and Radiation (BATAN) 2022-08-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1171 10.17146/aij.2022.1171 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 99-106 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1171/1018 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1426 2026-02-26T03:01:50Z aij:ART

Strategic Intelligence Analysis in The Integration of National Defense Components to Counter The Threat of Nuclear Terrorism in Indonesia Rajagukguk, M. H. Gunawan, B. Santoso, M. Ratmono, B. M. Intelligence Analysis; Intelligence Functions; Integration; Defense Components; Dual-Use; Nuclear Terrorism The development of nuclear science presents multifaceted benefits across diverse sectors, including energy, health, construction, agriculture, and food production. However, the proliferation of nuclear technology introduces the complex challenge of dual-use, encompassing both constructive applications and potential misuse for nefarious purposes such as terrorism. Indonesia, like many nations, faces this dual-use dilemma, necessitating robust defense mechanisms to safeguard against nuclear terrorism threats. This study aims to investigate and enhance Indonesia's defense system against nuclear terrorism by emphasizing integration and strategic intelligence within its defense components. The primary objective is to analyze the integration and coordination mechanisms among the main, supporting, and reserve components of Indonesia's defense system to strengthen strategic analysis and intelligence efforts in combating nuclear terrorism threats. Through a qualitative research methodology employing an analytical approach, data collection encompasses expert interviews, observations, and an extensive literature review. The study identifies various threat risks and potential initiators of nuclear terrorism attacks, highlighting the critical role of integrated defense components in addressing these threats effectively. Findings reveal the indispensable roles of the main, supporting, and reserve components in executing intelligence functions, including investigation, security, and information gathering, to mitigate the threat of nuclear terrorism. Despite their distinct roles, these components require seamless integration and coordination to maximize strategic analysis efforts and intelligence sharing. The research identifies several constraints hindering the effective implementation of integration and strategic intelligence within Indonesia's defense components. These constraints necessitate targeted improvements to enhance the nation's capability to mitigate the threat of nuclear terrorism effectively. In conclusion, this study underscores the significance of integration and strategic intelligence within Indonesia's defense system to confront the evolving threat landscape of nuclear terrorism. By addressing research gaps and proposing actionable recommendations, this research contributes to strengthening Indonesia's defense posture against nuclear terrorism, thereby ensuring national security and global stability. National Research and Innovation Agency 2025-09-18 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1426 10.55981/aij.2025.1426 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 195-205 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1426/1185 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1426/2662 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1426/2663 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1426/2664 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1228 2023-06-03T02:55:28Z aij:ART

The Quantitative Effect of Noise and Object Diameter on Low-Contrast Detectability of AAPM CT Performance Phantom Images Setiawati, E. Anam, C. Widyasari, W. Dougherty, G. Low-contrast detectability; Noise; Object diameter; SNR; CNR Parameters for determining computed tomography (CT) image quality include noise and low-contrast detectability. Studies on low-contrast detectability using the AAPM CT performance phantom have several limitations, such as the absence of quantitative information on the effect of noise and object size on low-contrast detectability. In this study, the quantitative effect of noise and object diameter on low-contrast detectability were investigated. Images of the American Association of Physicists in Medicine (AAPM) CT performance phantom model 610 were acquired with a tube voltage of 120 kV and tube currents of 50, 100, 150, and 200 mA. The low-contrast section of the AAPM CT performance phantom model 610 has objects with diameters between 2.5 and 7.5 mm. We analysed the mean CT number, noise level, signal-to noise ratio (SNR), and contrast-to-noise ratio (CNR), acquired using MatLab software. The results obtained indicate that noise and object size affect low-contrast detectability. The CNRs increase linearly with increasing of object diameter with R2 of 0.88, 0.67, 0.75, and 0.83 for tube currents of 50, 100, 150 and 200 mA, respectively. National Research and Innovation Agency Diponegoro University 2023-04-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1228 10.55981/aij.2023.1228 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 61-66 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1228/1067 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1228/2275 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1228/2276 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1228/2277 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1228/2278 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1228/2281 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1022 2021-01-05T08:21:55Z aij:ART

Calculation of Energy Levels and Reduced Electric Quadrupole Transition Probability for 22F Isotope Using Oxbash Code Hasan, A.K. Zayed, B.A. Nuclear shell model; Energy levels; Light nuclei; OXBASH code; SD-shell; PW and CWH interactions A study on the calculation of energy levels and reduced electric quadrupole transition probability for fluorine-22 isotope using Oxbash Code has been carried out. The shell model and OXBASH was used to calculate the energy levels and probability of quadratic transition B(E2) of the 22F isotope in the SD region through PW, CWH active interactions. A comparison was made between the calculation results and the experimental data. The comparison shows considerable consistency with the experimental results. The total angular momentum of the ground level 4+1 was confirmed when comparing with the experimental values. A significant consistency was obtained for the calculated energy values MeV (1.734, 2.387, 2.946) with the available experimental values of the same angular momentum (1+1,12+,4+2). It can be concluded that the reduced transition probabilities B(E2) can be  calculated using the PW, CWH reactions and OXBASH code. National Research and Innovation Agency 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1022 10.17146/aij.2020.1022 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 141–148 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1022/856 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1694 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1705 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1803 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1804 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1805 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1912 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1913 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1914 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1022/1915 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1309 2024-04-05T22:35:32Z aij:ART

Differential Cross Section With Volkov-Thermal Wave Function in Coulomb Potential Dhobi, S. H. Gupta, S. P. Yadav, K. Nakarmi, J. J. Jha, A. K. Born approximation; Volkov wavefunction; Volkov-thermal wavefunction; Differential cross section; Thermal electron Laser-assisted thermal electron-hydrogen atom elastic scattering was studied in the first-born approximation. The initial and final states of the projectile electron are described by the modified Volkov wavefunctions known as Volkov-Thermal wavefunctions. The laser-assisted thermal electron with energy ranges from 0.511 MeV to 4 MeV was considered to study the differential cross section (DCS) at azimuthal angles 30° and 14.7°, and laser-assisted field photon energy   1 eV to 3 eV are very weak at room temperature is around the room temperature 280 K to 300 K. The destructive interference was observed when a thermal electron absorbed a single photon from the laser field but no interference was found when a thermal electron emitted an electron to the laser field at a scattering angle . The DCS with eT scattering was found to be greater than a nonthermal electron in presence of laser field with scattering angle and incidence energy of the electron. National Research and Innovation Agency 2024-02-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1309 10.55981/aij.2024.1309 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 19-25 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1309/1107 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1309/2226 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1309/2379 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1309/2380 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1309/2381 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1309/2382 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1013 2021-08-30T07:42:43Z aij:ART

Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation Ardiansyah, H. Oktavian, M. R. Diffusion; Two-step method; IPWR; PARCS; Serpent Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost. This approximation has been used widely around the globe for various kinds of nuclear reactors. This diffusion approximation is applied in a two-step method, a method combining a high fidelity transport code and low fidelity diffusion code. Meanwhile, innovations in the nuclear core model continue to make the nuclear reactor core safer, more robust, and smaller. The trend of creating smaller and more modular reactor core is emerging in the last ten years. These innovations will affect the core modeling system. Consequently, for smaller reactors, it is important to evaluate the capability of diffusion approximation if one wants to use a computationally cheaper method to model the reactor core. In this paper, neutron diffusion calculation for 160 MWth integral pressurized water reactor (IPWR) core was conducted using the PARCS nodal diffusion code employing the few-group spatially homogenized cross-sections generated by the Serpent Monte Carlo code. Due to its capability to model any reactor geometry in the high-resolution calculation, the results from Serpent were also used as a reference. Two important parameters are compared between PARCS and Serpent: effective neutron multiplication factor and core power distribution. For the full IPWR core model, a discrepancy of 564 pcm between PARCS and Serpent keff was observed, while the radial power distribution had a maximum error of 4.71 %. It can be said, to some extent, that the diffusion approximation can be applied to IPWR core analysis. However, further improvement is indeed required if one wants more accurate results with low computational costs. National Research and Innovation Agency Lembaga Pengelola Dana Pendidikan (LPDP) 2021-07-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1013 10.17146/aij.2021.1013 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 85-92 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1013/977 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/1684 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/1692 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/2029 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/2030 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/2031 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1013/2032 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1513 2024-09-10T08:58:51Z aij:ACKv50no2

Acknowledgement Atom Indonesia Vol 50 No 2 ack50no2, ack50no2 National Research and Innovation Agency 2024-08-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1513 10.55981/aij.2024.1513 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1513/1131 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1119 2022-04-12T06:42:44Z aij:ART

Effect of Sub-energy Windows’ Parameters on the Triple Energy Window Scatter Correction Method Accuracy in 99mTc SPECT Imaging Saikouk, H. Khayati, N. E. Matrane, A. SPECT; GATE; Scatter correction; Triple energy window Scatter correction in SPECT quantification is of major importance to compensation for the scatter contribution under the photopeak. The triple energy windows method (TEW) is one of the suggested ways for scatter correction that are widely used in clinical routine. However, it can be a source of additional noise if the width or the number of sub-energy windows is not accurately chosen. To determine the precise scatter estimation windows settings under the 99mTc photopeak, scatter fraction was calculated for different sub-energy widths and numbers through GATE Monte Carlo simulation, for a main energy window of 15 %, centered at 140 keV. Four different acquisitions, with cold or hot inserts in a warm or a cold background, were studied. The estimation was done by two methods. The first method was the extraction of the number of detected Compton photons under the photopeak, therefore considered as the true scattered photons. The second method was the application of TEW method to the simulated energy spectra. The comparison of results corresponding to both methods shows a good agreement in two cases: simultaneous 7 % and 5 % sub-energy windows, respectively, positioned on the left and the right of the main energy window, and the second case is a 3 % left sub-energy window without a right sub-energy window. These sub-energy windows were then applied to experimental tomographic acquisitions to assess their impact on contrast, relative noise of the background (RNB), signal‑to‑noise ratio (SNR), integral uniformity (IU), and tomographic spatial resolution. Good results for these quantitative parameters were acquired with simultaneous 7 % and 5 % sub-energy windows. However, there was very little enhancement for tomographic spatial resolution. National Research and Innovation Agency National Center for Scientific and Technical Research (CNRST) Mohammed VI University Hospital, Nuclear Medicine Department Mohammed V University in Rabat, Faculty of Science 2022-04-04 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1119 10.17146/aij.2022.1119 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 51-59 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1119/1012 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2053 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2120 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2121 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2122 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2123 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1119/2124 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1645 2025-08-07T00:44:56Z aij:ART

Development of a Vietnamese PET/CT Dataset for Machine Learning-Based Analysis of Non-Small Cell Lung Cancer Images Tuan, H. Q. Duong, T. T. Ha, B. N. Quyet, N. H. Tinh, L. V. Tuynh, C. V. Nam, V. K. Dao, L. T. Q. Luong, C. V. Linh, D. T. M. Nhung, D. T. Nguyen, N. D. Trang, V. Q. Radiology, Nuclear Medince, PET-CT, Lung cancer, Machine learning. Positron Emission Tomography and Computed Tomography (PET/CT), a key imaging modality in nuclear medicine, Combines Anatomical (CT) and functional (PET) data for cancer diagnosis. Despite advancements in machine learning for automated medical image analysis, publicly available PET/CT datasets remain scarce, limiting Artificial Intelligence (AI) research compared to CT and MRI. This study built a publicly accessible PET/CT Vietnamese dataset for Non-Small Cell Lung Cancer (NSCLC). A total of 416 PET/CT scans were collected from three Vietnamese hospitals, including 300 NSCLC cases. Malignant FDG-sensitive lesions, identified via clinical PET/CT reports, were manually segmented in 3D (slice-by-slice) on PET images and validated by three experienced radiologists. The dataset includes both original and annotated DICOM files, along with clinical patient data. It achieved a dice similarity coefficient of 80.3 % and volume similarity of 81.9 %, demonstrating high segmentation accuracy comparable to other studies. This dataset supports AI-driven NSCLC research and contributes to global efforts in automated PET/CT analysis for nuclear medicine applications. National Research and Innovation Agency Vietnamese Ministry of Science and Technology 2025-07-21 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1645 10.55981/aij.2025.1645 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 137-143 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1645/1176 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1645/2739 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1645/2741 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1645/2742 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1645/2740 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1645/2747 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1243 2023-07-26T07:22:49Z aij:ART

A Modified Method for Increasing Radiochemical Purity of I-125 for Radiopharmaceuticals Maiyesni, M Mujinah, M Kurniasih, D. Witarti, W Hambali, H Febriana, S. Kambali, I. Iodine-125 radioisotope Impurities radiochemical purity radiopharmaceuticals the Jones reductor Iodine-125 (125I) is one of the radioisotopes widely used in radiopharmaceuticals for diagnosis and therapy of various cancers. Recent reports indicate that there has been shortages in the world supply of this radioiodine isotope. One of the absolute requirements good radiopharmaceuticals must meet is radiochemical purity, which generally has to be above 95 %, with an efficiency of over 90 %. The previous investigation shows that the radiochemical purity is low and does not meet the radiochemical requirement. In this work, we aim at improving the previous method by modifying the Jones reductor-based method. The modified method includes reduction and uniformization of Zn particle sizes, Zn particle compaction, and the performance of reduction process in a closed process flow. The Jones reductor converted impurities into products; in this case, iodate (IO3-) and periodate (IO4-) impurities were converted into iodide (I-), so that 125I product fulfills the radiochemical purity requirements and yielded high efficiency. In this investigation, the 125I previous product was, for the first time, improved with a radiochemical purity of 99.24 % and an efficiency of 97.98 %. National Research and Innovation Agency Maiyesni, Mujinah, D. Kurniasih, Witarti, Hambali, S. Febrianti, I. Kambali Batan 2023-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1243 10.55981/aij.2023.1243 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 1-5 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1243/1056 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1243/2142 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1243/2260 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1243/2261 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1243/2262 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1243/2279 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1956 2026-04-29T06:10:45Z aij:PRVv52no1

Preface Atom Indonesia Vol 52 No 1 Indonesia, Atom National Research and Innovation Agency 2026-02-26 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1956 10.55981/aij.2026.1956 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1956/1215 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/914 2020-09-25T01:39:20Z aij:ART

Molybdenum-99 (99Mo) Adsorption Profile of Zirconia-Based Materials for 99Mo/99mTc Generator Application Marlina, M Lestari, E. Abidin, A Hambali, H Saptiama, I. Febriana, S. Kadarisman, K Awaludin, R. Tanase, M. Nishikata, K. Tsuchiya, K. Low specific activity; Zirconia; Adsorption capacity; 99Mo/99mTc generator Technetium-99m (99mTc) plays a major role in diagnostic nuclear medicine and has not yet been replaced with any other radionuclides. It is available through the 99Mo/99mTc generator. The use of low-specific-activity 99Mo for 99Mo/99mTc generator application requires high adsorptive capacity sorbents. This study focused on the determination of 99Mo adsorption capacity of several zirconia materials, namely monoclinic nanozirconia, orthorhombic nanozirconia, sulfated zirconia,   and phosphated zirconia. These materials were synthesized by using the sol-gel method and characterized using FT-IR spectroscopy, X-ray diffraction (XRD), and scanning electron microscopy/energy-dispersive X-ray spectroscopy (SEM-EDS). The determination of 99Mo adsorption capacity of these materials was carried out by soaking the materials in a Na299MoO4 solution with pH of 3 and 7, at temperatures ranging from room temperature to 90 °C, for 1 and 3 hours. The results indicated that monoclinic nanozirconia has a 99Mo adsorption capacity of 76.9 mg Mo/g, whereas orthorhombic nanozirconia, sulfated zirconia, and phosphated zirconia have 99Mo adsorption capacities of 150.1 mg Mo/g, 15.58 mg Mo/g, and 12.74 mg Mo/g, respectively. It appears that orthorhombic nanozirconia has the highest 99Mo adsorption capacity among the synthesized materials and can be applied as a candidate material for the 99Mo/99mTc generator. National Research and Innovation Agency IAEA Coordinated Research Project F22068 (IAEA Research Contract No. 21033) M. Tanase, Oarai Research Center, Chiyoda Technol Corporation K. Nishikata, K. Tsuchiya, Oarai Research and Development Institute, Japan Atomic Energy Agency 2020-08-21 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/914 10.17146/aij.2020.914 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 91-97 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/914/841 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1310 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1338 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1366 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1367 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1454 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1617 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1618 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1619 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1859 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1860 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/914/1861 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1349 2023-12-19T03:11:18Z aij:ART

Comparative Analysis of Turbulence Models for Thermal-Hydraulic Simulations in Aqueous Homogeneous Reactors Pérez, D. M. Rodríguez, A. G. M. Lorenzo, D. E. B. de Oliveira Lira, C. A. Aqueous homogeneous reactors; Turbulence models; Reynolds-Averaged Navier-Stokes (RANS); Scale-Resolving Simulation (SRS) This article presents a comparative study of various turbulence models applied in the context of thermal-hydraulic simulations for liquid fuel reactors, specifically Aqueous Homogeneous Reactors (AHR) using Computational Fluid Dynamics. The objective was to assess the suitability of the turbulence models by comparing their results with data obtained from Large Eddy Simulation (LES). For that purpose, was compared the flow behavior predicted using the k-ε, SST, GEKO, DES, SBES, and LES turbulence models. The calculations were carried out in a simplified computational model derived from a pre-existing three-dimensional AHR conceptual design. By utilizing this simplified model, the study aimed to focus on the computational differences between the turbulence models, while minimizing the influence of other factors. The calculation results revealed that the k-ε model exhibited significant discrepancies with the LES, with relative differences for the fuel solution maximum temperature reaching up to 75 %. Among the remaining RANS models, the Shear Stress Transport (SST) model demonstrated the best compromise between accuracy and computational efficiency, with differences below 5 % and requiring only 1/5th of the time, compared to the LES model.  The Scale-Resolving Simulation (SRS) models,DES and SBES, provided a more comprehensive description of flow behavior and results closer to LES, albeit with higher computational demands. Between these two models, only the DES model exhibited relative differences below or equal to     1 % compared to the LES model for the studied thermohydraulic parameters. National Research and Innovation Agency Brazilian National Nuclear Energy Commission (CNEN), project no: 01341.011318/2021-51, and the Research Support Foundation of the State of Pernambuco (FACEPE), project number: BFP-0093-3.09/21. 2023-12-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1349 10.55981/aij.2023.1349 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 193-200 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1349/1098 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1318 2024-09-10T08:58:51Z aij:ART

A Neutronic Study of A Low-Enriched Uranium-Fueled Microreactor Cooled with A Sodium Heat Pipe System Using The OpenMC Code Bourenane, A. Hamidatou, L. Dougdag, M. Yahiaoui, M. L. OpenMC code; Neutronics; Microreactor; Power distribution The development of Small Modular Reactors (SMRs) represents a pivotal shift in nuclear technology, emphasizing enhanced safety, efficiency, and adaptability. This study examines Toshiba's MoveluX, an innovative micro-reactor, exemplifying advancements in reactor miniaturization suitable for limited spatial environments and hybridization with other energy sources. In this paper, the performance and safety of the MoveluX are rigorously evaluated using the OpenMC code, with an emphasis on critical parameters such as the effective multiplication coefficient and the reactivity worth of control devices. A 3D model of the given microreactor was built based on Toshiba's designs and features a solid core and a heat pipe cooling system. Preliminary results affirm the model's accuracy, and analysis of the neutron spectrum and flux indicates significant fission occurring in the U-238 isotope. Furthermore, the investigation extends to the thermal aspect within the fuel elements, uncovering a significant power density at the interfaces between fuel and moderator. Overall, this research makes a substantial contribution to the field of microreactor design and optimization. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1318 10.55981/aij.2024.1318 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 151-157 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1318/1123 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1318/2497 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1318/2498 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1318/2499 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1318/2500 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1318/2501 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1205 2021-12-14T05:39:27Z aij:PRVv47no3

Preface Atom Indonesia Vol 47 No 3 prf47no3, prf47no3 National Research and Innovation Agency 2021-08-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1205 10.17146/aij.2021.1205 Atom Indonesia; Vol 47, No 3 (2021): December 2021 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1205/1001 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1559 2025-04-14T03:30:31Z aij:ART

Selection of Bacteria from Mamuju’s NORM as Uranium and Thorium Bioleaching Agents Indryati, S. Mujiyanto, A. Widana, K. S. Hidayat, A. E. Rahma, F. J. Shabirah, C. A. Laksmana, R. I. Pratama, A. A. Trinopiawan, K. Prassanti, R. Purwanti, T. Putra, A. W. Sukadana, I G. Sugoro, I. Bacteria; Uranium; Thorium; NORM; Britholite; Ore; Radioactive; Bioleaching; Bacillus Natural materials that can cause increased radiation exposure to the surrounding environment are called Naturally Occurring Radioactive Materials (NORM). NORM contains uranium and thorium, critical elements with strategic and economic value. Conventional separation methods include chemical leaching and partial precipitation with strong acids and bases. These methods require large costs and produce waste harmful to the environment. This study explores bioleaching as an efficient and eco-friendly alternative to address these limitations. The indigenous bacteria used in bioleaching were isolated directly from NORM in Mamuju. This study aims to isolate, select, and evaluate bacteria from NORM as potential bioleaching agents. The methodology of this study includes NORM characterization, bacterial isolation and selection, molecular identification, and resistance testing of selected bacteria. The study successfully isolated eight bacterial strains from NORM, among which isolate L0A demonstrated the highest bioleaching potential. After five days of incubation, L0A achieved uranium and thorium concentrations of 2.508 mg/L and 10.5946 mg/L, respectively. Molecular identification revealed that L0A belongs to Bacillus sp. These findings demonstrate the potential of Bacillus sp. L0A is a bioleaching agent, paving the way for developing efficient, sustainable, and environmentally friendly methods for extracting valuable radioactive elements from NORM. National Research and Innovation Agency Research Center for Nuclear Materials and Radioactive Waste Technology-BRIN Reseacrh Center for Radiation Process Technology-BRIN 2025-04-11 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1559 10.55981/aij.2025.1559 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 81-86 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1559/1164 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1559/2666 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1559/2667 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1559/2668 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1559/2669 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1559/2670 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1186 2022-12-22T17:40:30Z aij:ART

Scanning Horn Simulation Code for Electron Beam Machine Based on Boris Algorithm Shali, A. H. Saminto, S Adabiah, S. R. Lucyana, F. Taufik, T Numerical simulation; Scanning horn; Irradiation distribution A numerical particle simulation code package to estimate the irradiation distribution of an electron beam machine is presented. Particle-to-particle interactions are calculated using particle-in-cell method, while the equation of motion is solved using Boris algorithm. The amplitude of oscillating magnetic field distribution from the scanning horn is obtained using CST magnetic field solver. The code was run using Intel’s i7-10700 processor without multithreading. For cases where particle-to-particle interactions are negligible, the simulation requires about 10 000 seconds to finish. The results show that different shapes of signals will result in different irradiation distributions. For a relatively low magnetic oscillation frequency, it is shown that a triangular signal will result in a more evenly distributed irradiation compared to a sinusoidal signal. National Research and Innovation Agency Center for Accelerator Science and Technology, National Nuclear Energy Agency (PSTA-BATAN) Center for Nuclear Facilities Engineering, Nuclear Energy Agency (PRFN - BATAN) 2022-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1186 10.17146/aij.2022.1186 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 205-213 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1186/1037 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1186/2146 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1186/2190 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1186/2191 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1186/2192 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1186/2193 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1528 2026-04-07T05:10:18Z aij:ART

Image Quality Assessment of Hybrid Statistical Iterative Reconstruction (H/SIR) in Comparison to Filtered Back Projection (FBP) Arjah, H. Osman, N. D. ALMasri, H. Anam, C. Aziz, M. E. Computed tomography; Low dose; Iterative reconstruction Hybrid Statistical Iterative Reconstruction (H/SIR) is a method for Computed Tomography (CT) image reconstruction that provides optimal diagnostic images while reducing radiation doses compared to the standard protocol using Filtered Back Projection (FBP). This work aims to assess the image quality metrics; Signal to Noise Ratio (SNR) and Contrast-to-Noise Ratio (CNR) of Low-Dose Computed Tomography (LDCT) examination with different vendors H/SIR algorithms. Three CT scanners from different manufacturers (Philips, GE, and Siemens) were used in this work. A total of 218 clinical images were analysed. The SNR and CNR of LDCT+H/SIR images were compared with standard protocol combined with FBP. The quantitative assessments were achieved by IndoQCT software. Results showed that H/SIR preserved image quality while radiation dose was minimized. National Research and Innovation Agency 2026-03-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1528 10.55981/aij.2026.1528 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 23-28 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1528/1203 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1528/2904 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1528/2905 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1528/2906 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1528/2907 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1333 2023-06-03T02:55:28Z aij:CVRv49no1

oai:ojs.aij.batan.go.id:article/1365 2023-08-29T08:24:47Z aij:CVRv49no2

Cover Atom Indonesia Vol 49 No 2 cvr49no2, cvr49no2 National Research and Innovation Agency 2023-05-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1365 10.55981/aij.2023.1365 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1365/1087 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/939 2021-06-28T15:53:36Z aij:ART

Safety Investigation of Hazardous Materials Released from the Combined High Temperature Gas Cooled Reactor – Hydrogen Production Plant Using ALOHA Software Priambodo, D. Sunarko, S Purwanto, W. W. Hydrogen; ALOHA; Hazardous material; Toxication; Flammable; Blast; Dispersion Safety Investigation of Hazardous Materials Released from The Combined High Temperature Gas Cooled Reactor (HTGR) – Hydrogen Production Plant Using ALOHA software has been carried out. Currently, most of studies for HTGR-hydrogen plant are focused only on the impact of hydrogen presence to the HTGR plant safety. Therefore, the objective of this study was to investigate the effect of the presence of natural gas and synthetic gas from Steam Methane Reforming hydrogen plant on the combine HTGR-Hydrogen production system using ALOHA software. Three selected hazardous materials: CH4, CO and H2 were analyzed. The selected potential hazards of the hazardous materials after leaking from the pipe were downwind suffocation/toxication, flammable area and blast area from vapor cloud explosion. Two types of parameter, i.e., meteorological dispersion (including wind speed, temperature, humidity, nuclear building air changes for day and night) and source release parameters (including pipeline length, and distance from the reactor building to the hydrogen plant), were selected for this study. The effects of the parameters on the hazard distance were then analyzed. The study shows that hydrogen detector needs to be installed at the plant to ensure safety of field operator. Furthermore, CO adsorber and H2 recombiner should be installed at the Reactor HVAC system for CO poisoning and H2 fire protection. Provision of a separation distance of more than 250 meters or construction of a blast barrier between the reactor building and the hydrogen plant is also recommended to protect the reactor from H2 explosion hazard. National Research and Innovation Agency 2021-04-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/939 10.17146/aij.2021.939 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 31-38 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/939/891 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1442 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1443 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1444 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1453 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1814 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1815 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1960 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1961 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1962 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1963 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/939/1964 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1344 2024-04-07T06:49:40Z aij:ART

Modeling of 137Cs Dispersion in the Atlantic Ocean at Ahanta West Coast: A Hypothetical Candidate Site for Ghana’s First Nuclear Power Plant Aggrey, Y. A. Amo-Boateng, M. Kpeglo, D. O. Muslim, M. Prasteyo, A. T. Ahanta west; Nuclear power plant; 137Cs; Rainy season; Dry season The government of Ghana has the intention of adding nuclear to its energy mix. Due to water availability for cooling, the coastal areas will be the right place for siting a nuclear power plant. This study was carried out to assess the distribution of 137Cs should liquid radioactive waste be released into coastal waters because of a non-routine event. The distribution was studied for the first month after the release. In the first week following the release, 137Cs was distributed within 16 km of the Ahanta West coastal waters with a concentration of about 9.1 Bq. L-1. On the seventh day, the distribution reached the entire coast of the Nzema East with a lower concentration with the bulk of the concentration still in the Ahanta waters. The 137Cs continued to spread into the eastern coast until the thirty-first day with a concentration of less than 1 Bq. L-1. This study provides useful data for future monitoring along the coast. National Research and Innovation Agency 2024-04-03 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1344 10.55981/aij.2024.1344 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 55-65 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1344/1112 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2396 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2397 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2399 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2400 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2401 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1344/2402 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1076 2021-12-10T07:11:49Z aij:ART

Gamma Radiation Shielding Properties of Slag and Fly Ash-based Geopolymers Hasan, M. W. Sugiharto, S. Astutiningsih, S. Geopolymer; Radiation Shielding; Attenuation Coefficient; Half-value Layer; Tenth-value Layer Industrial waste-based geopolymer cement is a greener alternative to Ordinary Portland Cement (OPC) for radiation shielding with comparable mechanical properties without the production of CO2 during synthesis. In this paper, the linear attenuation coefficient of slag and fly ash-based geopolymers, unmodified by aggregates, is measured and used to calculate the mass attenuation coefficients, half-value layer (HVL), and tenth-value layer (TVL) of the geopolymers. Narrow Beam Gamma Spectrometry with gamma energy of 0.662 MeV, 1.173 MeV, and 1.332 MeV was used to irradiate a series of slag and fly ash-based geopolymer paste of cylindrical shape with a diameter of 7.5 cm and height of 9.5 cm. Slag geopolymer has linear attenuation coefficient of 0.1642/cm, 0.1237/cm, 0.1150/cm, mass attenuation coefficient of 0.0782 cm2/g, 0.0589 cm2/g, 0.0548 cm2/g, the HVL of 4.222 cm, 5.609 cm, 6.056 cm, and TVL of 14.025 cm, 18.633 cm, 20.118 cm, respectively. Fly ash geopolymer has linear attenuation coefficient of 0.1387/cm, 0.1075/cm, and 0.0964/cm, mass attenuation coefficient of 0.0761 cm2/g, 0.0589 cm2/g, 0.0529 cm2/g, HVL of 4.998 cm, 6.453 cm, 7.202 cm, and TVL of 16.603 cm, 21.437 cm, 23.926 cm, respectively. Test samples made from slag-based geopolymers have a better shielding capability compared to fly ash-based geopolymers due to having higher attenuation coefficients as well as lower HVL and TVL, thus requiring less material to absorb radiation of the same energy level. National Research and Innovation Agency 2021-11-18 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1076 10.17146/aij.2021.1076 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 173-180 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1076/990 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1076/2076 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1575 2024-12-03T02:00:49Z aij:ACKv50no3

Acknowledgement Atom Indonesia Vol 50 No 3 Indonesia, Atom National Research and Innovation Agency 2024-09-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1575 10.55981/aij.2024.1575 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1575/1148 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1180 2025-05-07T03:15:29Z aij:ART

Investigation of Electron Contamination on Flattened and Unflattened Varian Clinac iX 6X and 15X Photon Beam Based on Monte Carlo Simulation Haryanto, F. Rhani, M. F. Anam, C. Yani, S. EGSnrc code; Electron contamination; Flattening filter; Flattening filter free; Monte carlo The aim of this study was to characterize electron contamination of a flattened (FF) and an unflattened (FFF) Varian Clinac iX 6X and 15X photon beams using Monte Carlo (MC) simulation. EGSnrc MC technique was used to model the flattened and unflattened head and simulate dose distribution of 6X and 15X of FF and FFF photon beam in water phantom. The materials and geometrical data of FF linac were provided by Tan Tock Seng Hospital (TTSH) Singapore. The FFF linac was modeled by removing the flattening filter component in the FF linac. Phase space files were scored after flattening filter and in the phantom surface. The phsp files were analyzed to characterize the particles produced by the linac head using BEAMDP. The contaminants contribute around 1 % and 2 % in the phsp1 for flattened and unflattened beams, respectively. The photons are scattered in small-angle in the range of 0 – 4o. The contaminant electron contributes up to one hundredth compared to the photons. The increase of field area affects the increase in contaminants and penumbra width due to the increasing number of particle scattered out of the field area. The unflattened beam affects the increase in the number of electron contamination and surface dose. The penumbra width of the flattened beams was smaller than the unflattened beams for the same field size and energy. National Research and Innovation Agency 2022-08-19 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1180 10.17146/aij.2022.1180 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 147-158 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1180/1029 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1180/2162 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1180/2163 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1180/2164 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1524 2026-02-26T03:01:50Z aij:ART

Measurement of Percentage Depth Dose using Fabricated Water Phantom Tank for 6 MV Photon Beam Alssnusi, A. M. Abdulla, Y. A. Hussein, N. A. El-Tashani, F. H. A. Local phantom; Percentage Depth Dose (PDD); Linac; Photon Beam Radiotherapy phantoms are utilized to estimate radiation dose delivered to patients, and to improve the accuracy and measurement of radiation dosimetry. The aim of this research is to measure the percentage depth dose (PDD) using a locally designed and fabricated water phantom tank as a cost-effective alternative to the commercially available water phantom used for calibrating therapeutic radiation doses from a linear accelerator. Acrylic material was used to construct the 30 × 40 × 30 cm3 water tank, and tests were conducted on the fabricated phantom using the Elekta linear accelerator at the National Cancer Center Benghazi (NCCB). An IBA FC65-P ionization chamber was used to measure the dose at depths ranging from 0 to 16 cm in 1 cm intervals for 6 MV photon energy at 10 x 10 cm2 field size, and 100 cm source surface distance (SSD). The results indicated that the dose values obtained from the locally fabricated water phantom closely matched those from the commercially installed water phantom and were consistent with values reported in the literature. National Research and Innovation Agency ٍSebha University , University of Benghazi, National Cancer Center Benghazi 2025-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1524 10.55981/aij.2025.1524 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 243-247 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1524/1194 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1524/2854 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1524/2855 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1524/2856 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1524/2857 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1524/2858 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1199 2023-08-29T02:15:31Z aij:ART

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX Nuryana, A. Mahmudah, R. S. N. Khakim, A. TRIGA 2000; MCNPX; Plate-type fuel; Neutronic parameter; Kinetic parameter A novel simulation to calculate the neutronic parameters of the TRIGA 2000 reactor using plate-type fuel has been performed. The plate fuel used was produced by the Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic parameters based on INUKI’s plate-type fuel dimension and the current TRIGA’s configuration were simulated using MCNPX. The simulation was performed by modeling the complete reactor’s configuration on a fresh fuel core state. We obtained the kinetic parameter values from the simulation, i.e., delayed neutron fraction of 8.11×10‑3, a prompt neutron lifetime of 2.0551×10‑4 s, and an average neutron generation time of 1.87×10‑4 s. The excess reactivity of the reactor was 9.02 %Δk/k, while reactivity in the one-stuck-rod state was below ‑0.5 $ with an average value of ‑3.40 %Δk/k (‑4.19 $). The average thermal neutron flux peak occurred at the central irradiation position with the value of 3.0×1013 to 3.1×1013 n/(cm2 s). The reactor has a power peaking factor of 1.379 in the control rod position of 0 % on D3 fuel. The reactor had a negative feedback reactivity coefficient, except for the moderator coefficient. These results suggest that the current configuration of plate-type fuel met the nuclear reactor neutronic safety standards. National Research and Innovation Agency 2023-06-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1199 10.55981/aij.2023.1199 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 77-88 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1199/1079 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2291 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2292 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2293 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2294 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2295 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1199/2296 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1073 2021-01-05T08:26:55Z aij:ART

Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400) Hartanto, D. Alshamsi, A. Alsuwaidi, A. Bilkhair, A. Hukal, H.A. Zubair, M. APR1400; Neutronics assessment; Accident tolerant fuel; Serpent; ENDF/B-VII.1 Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel system. This paper presents the investigation of the ATF system from a neutronics perspective, which positively reflects on the performance of the APR-1400 nuclear power plant. Several advanced fuel candidates such as UC, U3Si2, and UN, which have better thermophysical properties than current UO2 nuclear fuel, have been considered. Meanwhile, advanced cladding candidates such as FeCrAl, Zr-alloy with coating, and SiC which can reduce or even eliminate the oxidation rate of current Zr-alloy cladding have been adopted in this study. The Monte Carlo Serpent code, in conjunction with ENDF/B-VII.1 nuclear data library, has been used to calculate and evaluate the important neutronics parameters at the assembly level such as the fuel residence time, discharge burnup, kinetics parameters, pin power distribution, temperature reactivity feedbacks, and fissile evolution. The advanced fuels show better neutronics performance than the current UO2 fuel. In addition, SiC provides optimum neutronic performance as cladding. National Research and Innovation Agency A. Alshamsi, University of Sharjah A. Alsuwaidi, University of Sharjah A. Bilkhair, University of Sharjah H.A. Hukal, University of Sharjah M. Zubair, University of Sharjah. 2020-12-16 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1073 10.17146/aij.2020.1073 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 177 – 186 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1073/866 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1073/1916 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1073/1917 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1073/1918 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1111 2021-08-30T07:42:43Z aij:ART

An Automated Measurement of Image Slice Thickness of Computed Tomography Sofiyatun, S. Anam, C. Zahro, U. M. Rukmana, D. A. Dougherty, G. AAPM CT performance phantom; Automation; Computed tomography; Slice thickness Measurement of the slice thickness in computed tomography (CT) is usually made using a special phantom, such as the AAPM CT performance phantom. Images of the phantom are analyzed manually and subjectively. The purpose of this study is to develop an automated system for measuring the slice thickness of the CT image of the phantom using MATLAB software.The CT AAPM performance phantom was scanned by a 128 multi-slice computed tomography scanner (Revolution Evo, GE Healthcare, Waukesha, WI) at a slice thickness of 5 mm with four different phantom orientations and also scanned by a 6 multi-slice CT scanner (Somatom Emotion 6, Siemens AG, Forchheim, Germany) for two slice thicknesses of 5 and 10 mm. Our automatedmethod produced an accurateslice thickness value less than 0.5 mm different from the nominal slice thicknesses and manual measurements. Similar results were obtained when the phantom was rotated. This system is more objective and effective compared to manual systems. National Research and Innovation Agency Diponegoro University, Faculty of Sciences and Mathematics, Department of Physics 2021-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1111 10.17146/aij.2021.1111 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 121-128 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1111/982 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1111/1995 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1371 2025-01-19T14:07:15Z aij:ART

Comparison of the Thermo-Hydraulic Response of MELCOR 1.8.6 and 2.1 for SBO Accident for APR 1400 Reactor Ghaderinia, F. Rahgoshay, M. Jafari, J. Dauria, F. S. Severe accident, Station blackout, MELCOR, Containment failure, APR1400 An analysis of thermohydraulic response during a station blackout (SBO) accident for the APR 1400 nuclear power plant is performed using MELCOR version 1.8.6. MELCOR 1.8.6 results for the SBO scenario are benchmarked with MELCOR 2.1. The simulation of the SBO accident with MELCOR 2.1 was done by the APR 1400 reactor designer company (KEPCO). This research consists of two parts; the first part is related to the results of MELCOR 1.8.6, and the thermo-hydraulic analysis of MELCOR1.8.6 has been done. Analysis of thermohydraulic response is focused on investigating thermohydraulic parameters, such as core pressure, fuel clad temperature, water mass flow rate in the core, time of fuel clad failure, time of lower head failure, and time of containment failure. In the second part, the results of MELCOR version 1.86 have been benchmarked with the results of MELCOR 2.1. The results of the analysis of containment pressure changes in version 1.8.6 showed that the effect of pressure increase in containment is mostly due to the increase in carbon dioxide mass, but in version 2.1, the increase in pressure is more due to water vapor. National Research and Innovation Agency 2024-11-19 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1371 10.55981/aij.2024.1371 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 249-257 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1371/1140 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2550 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2551 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2552 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2553 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2554 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2556 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1371/2561 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1240 2022-04-13T13:06:06Z aij:ACKv48no1

Acknowledgement Atom Indonesia Vol 48 No 1 ack48no1, ack48no1 National Research and Innovation Agency 2022-03-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1240 10.17146/aij.2022.1240 Atom Indonesia; Vol 48, No 1 (2022): April 2022 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1240/1016 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1770 2025-08-07T00:44:56Z aij:PRVv51no2

Preface Atom Indonesia Vol 51 No 2 indonesia, atom National Research and Innovation Agency 2025-04-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1770 10.55981/aij.2025.1770 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1770/1182 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1230 2023-06-03T02:55:28Z aij:ART

A Two-Dimensional Unsteady FDTD Model for Radon Transport with Multiple Sources Emanation from Soil Layers Bezzout, H. El Ouardy, E. H. Meskini, N. El Faylali, H. Radon transport; Diffusion coefficient; Convection velocity; FDTD method; Radon multi-sources; Porous media A two-dimensional numerical model for radon transport based on the finite difference time domain (FDTD) method have been developed. The model is governed by the radon transport equation taking into account the mechanisms of diffusion, advection, and decay. The purpose of this model is to simulate the evolution of radon concentration which can be influenced by various parameters including depth and diffusion coefficient of the soil layer plus the velocity and initial concentration of radon. The obtained results were compared to an analytical solution to demonstrate the ability of this model for predicting the spatio-temporal evolution of radon transport in the porous media of soil layers. National Research and Innovation Agency 2023-03-31 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1230 10.55981/aij.2023.1230 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 33-38 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1230/1064 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1230/2267 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1230/2268 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1230/2269 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1230/2270 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1091 2020-08-31T11:46:24Z aij:PRVv46no2

Preface Atom Indonesia Vol 46 No 2 preface, preface National Research and Innovation Agency 2020-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1091 10.17146/aij.2020.1091 Atom Indonesia; Vol 46, No 2 (2020): August 2020 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1091/845 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1404 2023-12-19T04:17:01Z aij:PRVv49no3

Preface Atom Indonesia Vol 49 No 3 preface49no3, preface49no3 Rohandi National Research and Innovation Agency 2023-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1404 10.55981/aij.2023.1404 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1404/1103 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1142 2021-06-28T15:53:36Z aij:CVRv47no1

Cover Atom Indonesia Vol 47 No 1 cover47, cover47 National Research and Innovation Agency 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1142 10.17146/aij.2021.1142 Atom Indonesia; Vol 47, No 1 (2021): April 2021 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1142/900 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1419 2024-09-10T08:58:51Z aij:ART

Radiological and Toxicity Hazards Estimate of Drinking Water in Al-Diwaniyah, Iraq Abbas, M. A. Hammood, H. A. Salman, D. J. Radiological hazard; Toxicity hazard; Drinking water; Al-Diwaniyah city; CR-39; 222Rn In this work, analyses of 222Rn concentration and effective 226Ra content in all available types of drinking water in Al-Diwaniyah city, Iraq, were achieved by using CR-39 detectors technique. The annual effective dose from 222Rn and 226Ra distribution by three age groups were calculated. Radiological and chemical hazards were also calculated in drinking water samples. Drinking water samples were taken from tap water, water treatment plants, reverse osmosis water, and bottled drinking water in Al-Diwaniyah city. Effective 226Ra content level in some tap water samples were bigger than recommended value WHO for drinking water (1 Bq/L), but far below maximum acceptable limit of 370 Bq/L according to IAEA. All other values of 222Rn concentration and effective 226Ra content, annual effective dose, cancer morbidity and mortality hazards, and the lifetime average daily dose caused by consumption 226Ra in drinking water were less than recommended limits. Therefore, 222Rn concentration and effective 226Ra content in drinking water obtained in this work cannot give rise to radiological and chemical threats to population. However, for greater safety, we advise not to use tap water directly as drinking water. This work will provide important new data on the possible health effects of drinking water in Al-Diwaniya city. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1419 10.55981/aij.2024.1419 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 191-199 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1419/1127 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2378 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2470 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2471 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2472 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2473 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1419/2475 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1118 2022-04-12T03:55:44Z aij:ART

The Effects of High Level Natural Radiation in Mamuju - Indonesia on the Immune System of Its Residents Darlina, D Rahardjo, T. Surniyantoro, H. N. E. Rahajeng, N. Syaifudin, M. Immune response; IgE; Natural radiation; ELISA; Mamuju The immune system is one of the most significant defenses against environmental insults including natural radiation. The purpose of this preliminary study was to assess the effects of high natural radiation to Mamuju residents, by focusing on immune-related blood cell counts (leukocytes, lymphocytes, monocytes, and granulocytes) and immunoglobulin E (IgE) level. The blood samples were collected from 18 adult residents in a high background radiation area (HBRA) while 18 residents in a normal background radiation area (NBRA) served as a control group. The blood components were measured by using the hematopoietic analyzer, and IgE immune biomarker was measured with ELISA (enzyme-linked immunosorbent assay) according to standard protocols. The data showed that the level of all blood cells, except for monocytes, of residents in HBRA was higher than that of NBRA. Statistical analysis revealed that there was no significant difference (P0.05) in the blood cell counts and IgE level in both groups and their values were within normal limits. The level of IgE in HBRA was significantly higher than the control area (P≤0.05), as its IgE level in males compared to females in both residents. The relationship between IgE level and age were negative in these residents. From this study, it was concluded that long-term exposure to high radiation may affect the immune system as one of radiation adaptive response. National Research and Innovation Agency Center for Radiation Safety Technology and Metrology, National Nuclear Energy Agency of Indonesia (BATAN) 2022-03-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1118 10.17146/aij.2022.1118 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 21-27 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1118/1008 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/1921 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/1922 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2054 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2060 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2073 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2106 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2107 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2108 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1118/2109 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1580 2025-08-07T00:44:56Z aij:ART

Brain Tumor Segmentation in MR Images Using Swin Transformer Nur, A. Nurhanafi, K. Putri, E. R. Artificial intelligence; Brain tumor; Magnetic Resonance Imaging (MRI); Segmentation; Swin transformer. Brain tumors are abnormal tissue growths in the brain. These brain tumors can have a negative impact on human health, one of which can interfere with brain functions such as vision, balance, and so on. Therefore, early detection needs to be done, one of which is by using medical imaging modalities, i.e., MRI. However, analyzing MRI scans requires careful observation and a high level of proficiency. Thus, medical image segmentation is required. Segmentation is important in medical image analysis as it allows medical experts to distinguish between abnormal and normal tissues. This study aims to determine the ability of the swin transformer architecture in segmenting brain tumor MR images. The image data used was BraTS 2021 data with a total of 1,250 images. The data were divided into three, i.e., training set, validation set, and testing set with a ratio of 70:15:15. Swin Transformer provided two main concepts, i.e., hierarchical feature maps and attention window shifts. The Swin Transformer initially was divided the image into small patches, which were then converted into vector form. After that, it was passed through W-MSA for local area and SW-MSA for cross window area. Next, multiple patches were merged into one, so that the image resolution gradually decreased, and then restored back to the original resolution. Based on this, the segmentation results were evaluated using a confusion matrix using DSC, IoU, and sensitivity metrics. The results of brain tumors MR image segmentation with Swin Transformer obtained evaluation values, i.e., 0.97313 for DSC, 0.94767 for IoU, and 0.96450 for sensitivity. It can be concluded that the Swin Tranformer can effectively segment brain tumor MR images. National Research and Innovation Agency 2025-05-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1580 10.55981/aij.2025.1580 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 97-108 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1580/1169 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2675 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2680 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2681 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2682 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2683 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1580/2684 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1169 2022-12-28T23:29:51Z aij:ART

Response Surface Optimization of Gamma Irradiation Synthesis of Alginate-Stabilized Silver Nanoparticles Without Addition of a Hydroxyl Radical Scavenger Perkasa, D. P. Arozal, W. Kusmardi, K Syaifudin, M. Silver nanoparticles; Alginate; Gamma irradiation; Response surface methodology; Optimization The use of isopropanol as a hydroxyl radical scavenger on the radiosynthesis of alginate-stabilized silver nanoparticles (AgNPs) can limit its application in nanomedicine. Meanwhile, optimum condition for gamma irradiation synthesis of alginate-stabilized AgNPs without addition of a hydroxyl radical scavenger has not been reported yet. In this study, the optimization of this process was carried out using response surface methodology (RSM) combined with Central Composite Design (CCD). The three processing conditions, i.e. radiation dose, precursor silver ion concentration, and alginate concentration were selected as decision variables to maximize two responses in terms of the conversion yield and AgNP concentration responses. The results indicated that the regression model of conversion yield and AgNP concentration fit linearly with the two-factor interaction and the linear model, respectively. The significant effect of the alginate factor on the conversion yield indicates the dual stabilizing–scavenging role of the alginate. The optimum conditions derived from CCD-RSM were obtained at a 20 kGy radiation dose, 7.78 mM precursor silver ion concentration, and 1.2 % (w/v) alginate concentration with the desirability of 0.731. The actual experimental results were 65.43% conversion yield and 480.91 ppm AgNP concentration, which were within the prediction interval at confidence of 95 %. The AgNPs under the optimum condition had a spherical shape, 97.4 % volume of size distribution at 6.50-28.21 nm, and zeta potential of -28.3 mV. National Research and Innovation Agency Universitas Indonesia Center for Application of Isotopes and Radiation, National Nuclear Energy Agency Center for Nuclear Mine Technology, National Nuclear Enery Agency – Republic of Indonesia 2022-12-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1169 10.17146/aij.2022.1169 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 247-257 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1169/1052 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1169/2048 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1169/2215 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1169/2216 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1564 2026-04-02T09:36:37Z aij:ART

Estimating TPR₂₀,₁₀ Under Non-Reference Conditions Using a Geometric Sequence Approach Rizaldi, F. A. Herwiningsih, S. Widodo, C. S. Hentihu, F. K. Anto, A. K. TPR20,10 under reference conditions; TPR20,10 under non-reference conditions; Beam quality test of linear accelerator; Geometric sequence approach; X-ray megavoltage photon beam; An alternative approach to estimate the Tissue Phantom Ratio (TPR) at depths of 20 cm and 10 cm (TPR₂₀,₁₀) under non-reference conditions is required to address situations where a 10 × 10 cm² field size is not achievable on a specific Linear Accelerator (LINAC) during a beam quality test. This study aims to estimate the TPR20,10 under non-reference conditions using a geometric sequence approach, and to compare it with the TPR₂₀,₁₀ under non-reference conditions estimated using the Sauer method, the Palmas method, a linear fit approach, as well as with the TPR₂₀,₁₀ under reference conditions calculated using the TRS-398 protocol. The first step in this study was measuring the percentage depth dose (PDD), D20cm, and D10cm with field size variations from 4 × 4 cm² to 10 × 10 cm² for both 6 MV and 10 MV X-ray beams. The PDD were used to estimate the TPR₂₀,₁₀ using a geometric sequence approach, the Sauer method, the Palmans method, and a linear fit approach, and to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The D20cm and D10cm were also used to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach were 0.683 ± 0.004 and 0.742 ± 0.005, respectively. The level of precision that could be reached by the geometric sequence approach is potentially equivalent to the TRS-398 protocol, the Sauer method, the Palmans method, and the linear fit approach. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence method did not show a significant difference compared with the TPR₂₀,₁₀ calculated using the TRS-398 protocol. However, the TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach showed a significant difference compared with those TPR₂₀,₁₀ estimated using the Sauer method and the Palmans method. National Research and Innovation Agency Brawijaya University, Physics Department Lavalette Hospital, Radiotherapy Department 2026-03-31 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1564 10.55981/aij.2026.1564 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 73-79 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1564/1210 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2557 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2558 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2603 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2678 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2679 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2938 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2939 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2940 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1564/2941 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/745 2020-09-25T01:50:56Z aij:ART

Radiolabeling Technique of Silver Nanoparticles (AgNPs) with Iodine-131 Radionuclide Sholikhah, U.N. Syahdi, R.R. Permatasari, S.E. Sarmini, E. Sriyono, S Widyaningrum, T. Gamma counter; Radiochemical purity; Radionuclide purity; Radiotheraphy  Radiotherapy is an effective cancer therapy, where a certain dose of radiation is aimed specifically at target and is unaffecting to normal tissue. A selectiveradionuclide must be attached to the specific targeted organ. In this research, silver nanoparticles (AgNPs) were labeled with radionuclide of iodine-131 (131I) to be used in radiotherapy. Silver nanoparticles were synthesized using silver nitrate 0.0005 M, sodium borohydride 0.002 M, polyvinylpyrrolidone 0.3 % (w/v) and natrium chloride 1.5 M, and then followed by purification by centrifugation. Characterization was carried out with UV-Vis spectrophotometer, transmission electron microscope, particle size analyzer, and zeta-sizer. The results show that the maximum absorbance is on a wavelength of 398 nm, spherical shape with a diameter of 10 nm, polydispersity index of 0.455, and zeta potential value of –8 mV. The radiolabeling was done by adding sodium iodide-131 which had been oxidized by chloramine-T and immobilized in AgNPs colloidal solution, and the activity was then measured using a dose calibrator. The identification of radionuclide showed that the sample was free of impurities. The optimum system of radiochemical purity was obtained using Whatman 1 paper strip as the stationary phase and a mixture of methanol: water: ammonium acetate (1:1:1) as the mobile phase, which gave 96 % purity. This method is suitable for radiolabeling AgNPs with 131I to be used for radiotherapy. National Research and Innovation Agency National Nuclear Enegry Agency 2020-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/745 10.17146/aij.2020.745 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 63-68 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/745/837 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/773 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/864 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1197 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1267 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1341 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1458 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1706 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1738 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1856 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1857 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/745/1858 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1341 2023-12-19T03:11:18Z aij:ART

The Effect of Sr2+ and Fe3+ Cations and the Stirring Speed on The Precipitation of Barium Sulfate in a Batch System Susilowati, S Karaman, N. Prayuga, A. R. Aruba, D. T. Sukirmiyadi, S Suprianti, L. Barium sulfate; Batch system; Cation; Precipitation rate The batch system investigation explored the effect of Sr2+ and Fe3+ cations and the stirring speed on the characteristics of precipitated barium sulfate. A series of experiments were conducted to evaluate the rate of barium sulfate precipitation in laboratory equipment from brines containing barium ions (3500 ppm) and varying amounts of Sr2+ and Fe3+ ions (10 and 20 ppm). Kinetic analysis was also performed to explore how stirring speeds (240 and 480 rpm) affect barium sulfate scales' crystallization by increasing the stirring speed and promoting Sr2+ and Fe3+-cation solubility while decreasing the precipitation rate. All solid crystals obtained were mostly pure barite, as the X-ray diffraction (XRD) method confirmed. The SEM micrograph of barite morphology revealed particles with tablet-shaped crystals 2 to 5 nm in size. With the presence of Sr2+ and Fe3+-cation, the shape of barium sulfate was modified into spherical tablets or flower-like clusters of tablets. Meanwhile, the morphological changes could result from increased stirring rates. Moreover, the kinetic results yielded a general reaction rate equation that might be used to estimate barium sulfate deposition in pipelines for various brine, supersaturation, and mixing time durations. National Research and Innovation Agency 2023-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1341 10.55981/aij.2023.1341 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 159-167 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1341/1093 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1341/2343 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1341/2344 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1341/2345 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1450 2024-04-05T10:03:52Z aij:ACKv50no1

Acknowledgement Atom Indonesia Vol 50 No 1 Yusuf, Anggiana Rohandi National Research and Innovation Agency 2024-02-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1450 10.55981/aij.2024.1450 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1450/1117 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1110 2021-12-10T07:15:22Z aij:ART

Dosimetric Assessment of Routine X-Ray Examination at Selected Health Clinics in Perak Using Commercialized Optically-Stimulated Luminescence Dosimeter (OSLD) Saidin, M. T. Rahman, A. A. Harun, H. H. Radzi, Y. M. Anam, C. Kayun, Z. Diagnostic reference level; Entrance surface dose; Optically-stimulated luminescence; Dosimeter; Chest X-ray This study aims to compare entrance surface dose (ESD) values measured with nanoDot Al2O3:C optically-stimulated luminescence dosimeter (OSLD) and guidance level set under the second national dose survey which utilized old-version LiF:Mg,Ti thermoluminescence dosimeter (TLD). In this study, we conducted a dosimetric assessment for posteroanterior chest X-ray (PA-CXR) examinations performed at various community clinics in Perak, Malaysia. These clinics were selected as they were excluded from the first and second national dose survey conducted in Malaysia in 1993-1995 and 2005-2009, respectively. The ESD is obtained by mounting the OSLD on the surface of polymethyl methacrylate (PMMA) slabs. The PMMA slabs were then exposed to X-ray based on the current practice of respective clinics. The results show that the 3rd quartile of ESDs ranged from 0.180 mGy to 0.229 mGy which is less than the recommended guidance level of the second national dose survey by 77 %. ESD measured using OSLD was found to be lower than the guidance values recommended from the second national dose survey. The finding showed a good competency of the radiographer to optimize radiological practice specifically in routine X-ray examination. National Research and Innovation Agency 2021-12-03 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1110 10.17146/aij.2021.1110 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 213-218 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1110/992 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1110/2081 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1110/2082 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1110/2083 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1110/2084 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1517 2025-04-14T03:30:31Z aij:ART

Determination of Typical Values for Pediatric Head CT Scan at Universitas Andalas Hospital Fardela, R. Delvihardini, R. Pratama, I. B. G.P. Milvita, D. Oktavia, A. CT Scan; CTDIVol; DLP; Typical value The utilization of X-rays in the Computed Tomography Scaner (CT scan) modality has proliferated for diagnostic purposes. CT scans deliver higher doses than other modalities, consequently protecting patients from excessive radiation doses is necessary by increasing optimization efforts in patients, especially pediatric patients. This research aims to determine the typical value and analyze the correlation of age, body mass, and exposure factor (mAs) to Computed Tomography Dose Index Volume (CTDIVol) and Dose Length Product (DLP). The typical dose value was obtained from the median value (Q2) using data derived from pediatric patients undergoing a head CT scan with a total of 33 patients at Universitas Andalas Hospital, with a correlation determined using a linearity test. The results obtained were the typical value for CTDIVol of 31.1 mGy and DLP of 793.3 mGy.cm. There is a moderate correlation between age and CTDIVol and DLP values, a high correlation between body mass and CTDIVol and DLP values, and a very high correlation between the exposure factor (mAs) and CTDIVol and DLP values. National Research and Innovation Agency The present study was funded and facilitated by Universitas Andalas, in accordance with the Undergraduate Thesis Research contract (PSS) Batch I Number: 229/UN16.19/PT.01.03/PSS/2024, fiscal year 2024 2025-03-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1517 10.55981/aij.2025.1517 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 51-56 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1517/1158 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2512 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2513 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2514 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2646 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2647 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2648 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1517/2649 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1113 2022-12-22T17:40:30Z aij:ART

Noise Suppression of Computed Tomography (CT) Images Using Residual Encoder-Decoder Convolutional Neural Network (RED-CNN) Cokrokusumo, H. B. Hariyati, I. Lubis, L. E. Prajitno, P. Soejoko, D. S. Deep learning; Encoder-decoder network; Fully convolutional network; Image denoising; Low-dose CT; Residual network In this study, an in-house residual encoder-decoder convolutional neural network (RED-CNN)-based algorithm was composed and trained using images of cylindrical polymethyl-methacrylate (PMMA) phantom with a diameter of 26 cm at different simulated noise levels. The model was tested on 21 × 26 cm elliptical PMMA computed tomography (CT) phantom images with simulated noise to evaluate its denoising capability using signal to noise ratio (SNR), comparative peak signal-to-noise ratio (cPSNR), structural similarity (SSIM) index, modulation transfer function frequencies (MTF 10 %) and noise power spectra (NPS) values as parameters. Evaluation of a possible decrease of image quality was also performed by testing the model using homogenous water phantom and wire phantom images acquired using different mAs values. Results show that the model was able to consistently increase SNR, cPSNR, SSIM values, and decrease the integral noise power spectra (NPS). However, the noise level on either training or testing data affects the model’s final denoising performance. The lower noise level on testing data images tends to result in over-smoothed images, as indicated by the shift of the NPS curves. In contrast, higher simulated noise level tends to result in less satisfactory denoising performance, as indicated by lower SNR, cPSNR, and SSIM values. Meanwhile, the higher noise level on training data images tends to produce denoised images with reduced sharpness, as indicated by the decrease of the MTF 10 % values. Further studies are required to better understand the character of RED-CNN for CT noise suppression regarding the optimum parameters for best results. National Research and Innovation Agency Indah Lestariningsih, Cibinong Regional General Hospital 2022-11-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1113 10.17146/aij.2022.1113 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 171-178 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1113/1036 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2118 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2119 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2169 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2170 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2171 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1113/2172 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1875 2026-02-26T03:01:50Z aij:PRVv51no3

Preface Atom Indonesia Vol 51 No 3 indonesia, atom National Research and Innovation Agency 2025-08-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1875 10.55981/aij.2025.1875 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1875/1199 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1322 2023-04-27T03:24:05Z aij:ACKv49no1

oai:ojs.aij.batan.go.id:article/1300 2023-09-05T00:14:07Z aij:ART

Elemental Mapping and Quantities in Different Soybean Seed Colors Using Micro X-Ray Fluorescence and Their Correlations with Germination Wibisono, K. Nurcholis, W. Element quantities; Elemental mapping; Micro X-ray fluorescence; Seed germination; Soybean seed Micro X-ray fluorescence (μ-XRF) possesses a powerful analytical technique able to detect macro- and micro-elements. Each plant variety has a unique elemental composition and important role in the germination process. The aims of this study were to (1) map the elements and quantities in the soybean seed coat and endosperm, (2) investigate how the various elements might mediate the inter-relationship or correlation between elements within soybean seed genotypes with different seed coat colors, and (3) investigate that the targeted morphological characteristics especially in germination would be affected by seed elements. A μ-XRF technique was used for the elemental analysis and quantification. Three genotypes of Indonesian soybean were used in this study: greenish, black, and yellowish. In this study, we found that the silicon (Si) and magnesium (Mg) elements have a significant correlation. The high quantity of Si element in the embryo axis has a positive correlation with root length. The high quantity of Mg element which is evenly distributed on the endosperm has a positive correlation with normal germination. Si and Mg elements in the seeds have a negative correlation with imbibition water absorption. Based on the comparison between the three genotypes, the black genotype was superior in terms of germination and higher Si and Mg elements. Thus, the Si and Mg elements can be used as a reference in determining superiority of genotypes at the germination stage. National Research and Innovation Agency 2023-08-11 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1300 10.55981/aij.2023.1300 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 115-123 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1300/1080 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1300/2322 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1300/2323 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1300/2324 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1023 2021-06-28T15:53:36Z aij:ART

Study of Dried and Calcinated Ceria Stabilized Zirconia Microspheres Morphology by Small-Angle X-Ray Scattering and Optical Microscopy Patriati, A. Insani, A. Suparno, N. Hutamaningtyas, E. Soontaranoon, S. Mujamilah, M CSZ; SAXS; Microsphere; Nuclear fuel; External gelation The knowledge of how to avoid crack at high temperature is crucial in fuel fabrication for Experimental Power Reactor or Reaktor Daya Eksperimental (RDE). This knowledge should be established and well-mastered by BATAN. RDE uses uranium dioxide as its nuclear fuel. However, uranium utilization for research purposes is heavily restricted. Therefore, the fabrication of ceria-stabilized zirconia (CSZ) microspheres as nuclear fuel surrogate was studied. In this work, the CSZ was prepared by external gelation with two different washing solutions, i.e. isopropyl alcohol (IPA) and propylene glycol methyl ether (PGME). The morphology in nano- and micro-scale of each CSZ microspheres from both variations was evaluated by small-angle x-ray scattering (SAXS) and optical microscopy. The morphology of the CSZ microsphere after drying at 80 °C and calcination at 200 °C were observed to understand the structural change in those steps and to see the potential crack based on its morphology. There are two parameters that can prevent microspheres from cracking at high temperatures for the next process, i.e., porosity and gel texture. It was observed that IPA solution has a benefit as a washing solution as it can trigger more porosities in the microspheres, but less in gel texture. National Research and Innovation Agency Ministry of Research and Technology and Higher Education of Indonesia 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1023 10.17146/aij.2020.1023 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 5-10 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1023/886 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1023/1711 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1023/1948 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1023/1949 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1023/1950 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1023/1954 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1176 2021-08-30T07:42:43Z aij:PRVv47no2

Preface Atom Indonesia Vol 47 No 2 preface472, preface472 National Research and Innovation Agency 2021-06-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1176 10.17146/aij.2021.1176 Atom Indonesia; Vol 47, No 2 (2021): August 2021 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1176/974 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1502 2024-12-03T02:00:49Z aij:ART

Estimation of Organ Dose, Effective Dose, and Cancer Risk in Abdominal CT Scan Patients Putri, S. S. Intifadhah, S. H. Putri, E. R. Abdomen; Cancer risk; CT scan; Effective dose; Organ dose Computed tomography scan (CT scan) is a modality that is used to diagnose diseases inside the human body. In the scanning process, the patient will receive radiation from the CT scanner, so that it is necessary to calculate the amount of radiation dose. The purpose of this study was to determine the organ dose, effective dose, and cancer risk received by abdominal examination patients. Data taken from the results of abdominal examination patients at Radiology Installation of A.W. Sjahranie Regional Hospital Samarinda using 16-slice CT scan modality GE BRIVO type D3161T. The data collected included 150 patients, both female and male, with ages ranging from 15 to 79 years. Dosimetry parameters taken from CT scan results are the exposure factor (kV, mAs), scan length, computed tomography dosimetry indeks volume (CTDIvol), and dose length product (DLP) of the patient. CTDIvol and DLP of the patient are used to calculate the organ dose, effective dose, and cancer risk values of abdominal CT scan patients. Then the effective dose value received by the abdominal CT scan examination patient is compared with the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) standard based on the CTDIvol and DLP values of the patient, and also compared with the International Commission Radiological Protection (ICRP) standard. Based on the results of organ dose estimation calculations, the average value of the stomach is 0.82 mSv, the gonads are 0.54 mSv, and the bladder is 0.28 mSv. Meanwhile, the average value of effective dose received by abdominal examination patients is 5.28 mSv with an average cancer risk of 0.029 %. Based on the CTDIvol and DLP values of the patients, the 3rd quartile values of the patients were 8.25 mGy and 413.84 mGy.cm. This value is still below the value recommended by BAPETEN when viewed from the 2021 Diagnostic Reference Level (DRL) guidelines. The effective dose received by one patient exceeded the standard set by the ICRP. Meanwhile, the cancer risk received by patients is still in a low percentage. National Research and Innovation Agency 2024-11-26 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1502 10.55981/aij.2024.1502 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 289-294 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1502/1146 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1502/2584 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1502/2585 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1502/2586 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1502/2587 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1198 2022-08-24T21:12:05Z aij:ART

Identification, Selection, and Response of Radiation Induced Towuti Mutant Rice (Oryza Sativa L.) in Drought Stress Conditions Dama, H. Aisyah, S. I. Sudarsono, S Dewi, A. K. Wibisono, K. Drought stress; Gamma-rays; Characters selection; Stay-green gene; Rice mutant Climate change with the impact of drought stress has become a major environmental problem for rice (Oryza sativa L.). The use of gamma ray radiation at a dose of 300 Gy is one way to develop drought tolerant rice varieties with little change to the characteristics of the Towuti variety. However, research is still needed to determine its resistance to drought stress. This study aims to identify characters for selection, genotype selection, and determine the response of Towuti mutant rice to drought stress conditions.The characters that can be used to select rice genotypes under drought stress conditions are plant height, number of leaves, number of tillers, and SPAD chlorophyll value. The Towuti mutant has the best tolerance to drought stress compared to other genotypes. Tolerance to drought stress in the Towuti mutant is not caused by the stay-green gene. National Research and Innovation Agency 2022-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1198 10.17146/aij.2022.1198 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 107-114 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1198/1022 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1198/2155 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1198/2156 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1198/2157 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1618 2026-02-26T03:01:50Z aij:ART

Verification of Breast Cancer Treatment Planning with Various Radiation Techniques Using Monte Carlo Simulations and Linac Log Files Sugandi, R. D. Azzi, A. Fadli, M. Sihono, D. S. K. Dynalog files; Monte carlo; Patient-specific quality assurance; Radiotherapy Due to the complexity of radiotherapy techniques, rigorous Patient-Specific Quality Assurance (PSQA) is crucial to ensure the accuracy of treatment plans. This study aims to evaluate the performance of the Treatment Planning System (TPS) by comparing its dose distribution calculations with those obtained from the PRIMO Monte Carlo simulation. Treatment plans for 3D-CRT, IMRT, and VMAT were generated for a Rando breast phantom using the TPS. Subsequently, the dose distributions from the TPS were compared with those obtained from the PRIMO Monte Carlo simulation. Key metrics, including Homogeneity Index (HI) and Conformity Index (CI), were calculated to assess the quality of dose distribution. Furthermore, the dose constraints on OARs were evaluated to assess the impact on surrounding healthy tissues. To further validate the TPS, dose distributions from the linac log file (Dynalog) for VMAT were reconstructed within the PRIMO environment. These reconstructed distributions were then compared with the dose distributions calculated directly by the TPS. Gamma index analysis was employed to evaluate the agreement between these two sets of data. The comparison between TPS and Monte Carlo simulations revealed that 3D-CRT plans exhibited smaller deviations in HI and CI compared to IMRT and VMAT plans. However, a significant improvement in HI and CI values was observed in both IMRT planning simulations and Dynalog VMAT file simulations, indicating enhanced plan quality. The dose received by OARs in all treatment plans remained within the acceptable dose thresholds, demonstrating effective sparing of surrounding healthy tissues. For the PSQA procedure, the 3D-CRT technique is still the safest due to its lower level of complexity compared to IMRT and VMAT. More complex treatments should consider the robustness of treatment transfer information from TPS to linac to avoid dosimetry errors. National Research and Innovation Agency 2025-09-29 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1618 10.55981/aij.2025.1618 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 207-213 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1618/1186 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1618/2797 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1618/2798 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1618/2799 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1618/2800 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1618/2801 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1337 2023-06-03T02:56:49Z aij:PRVv49no1

Preface Atom Indonesia Vol 49 No 1 prfc49no1, prfc49no1 National Research and Innovation Agency 2023-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1337 10.55981/aij.2023.1337 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1337/1077 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/983 2020-12-16T02:45:17Z aij:ART

Reactivity Initiated Transient Response of TRIGA with the Progress of Core Burnt Haque, F. Badrun, N.H. EUREKA-2/RR; COOLOD-N2; TRIGA core; Burnt; Reactivity; Insertion duration This paper illustrates the effects on safety of TRIGA Mark-II research reactor of Bangladesh at its different steps of core burnt during reactivity induced transient. The modeling and simulation were carried by coupled point kinetics, neutronics, and thermal hydraulics code EUREKA-2/RR based on neutronics data calculated previously by Monte Carlo code for different burnt states of TRIGA core. Three burn steps until 150 MWD have been considered for present analysis which are regarded here as beginning of cycle (BOC); middle of cycle, MOC (75 MWD); and end of cycle, EOC (150 MWD). Initially, the results of steady state analysis obtained from EUREKA code for these three burn steps have been verified with that of COOLOD code. Based on consistency of the results from the two codes, transient simulation has been conducted considering reactor with non-function of scram. Reactivity inserted amount ranges within 0.001 to 0.02 dk/k with three durations of insertions of 0.1s, 1s, and 5s. Major parameters such as reactor core maximum power and fuel clad maximum temperature have been reported. The analysis presents transient pattern of these parameters due to change in amount and duration of inserted reactivity. The maximum imposed reactivity that causes the fuel clad to exceed its design temperature at each burn step has been evaluated in this study. It is also observed here for each amount and durations of inserted reactivity, maximum value of both power and clad temperature found to decrease with the progress of core burnt. These results obtained from this analysis will be useful for reactor operators and management team during core upgrading and modification program. National Research and Innovation Agency 2020-12-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/983 10.17146/aij.2020.983 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 149-154 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/983/860 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1595 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1600 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1613 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1707 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1732 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1733 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1734 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1735 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1827 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1830 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1833 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1886 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1887 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1888 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/983/1889 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1311 2024-04-05T22:36:37Z aij:ART

Monte Carlo Methods to Simulate the Propagation of the Created Atomic/ Nuclear Particles from Underground Piezoelectric Rocks through the Fractures Before the Earthquakes Bahari, A. Mohammadi, S. Shakib, N. S. Benam, M. R. Sajjadi, Z. MCNP; Granite rocks; Earthquake; Particles radiation; Gamma ray; Neutrons; Runaway electrons Until now, many studies have been performed on particle radiations before or during earthquakes (EQs). Neutron, gamma, electron, proton, and ultra-low frequency (ULF) photons are among the particles, detected during EQs. In our previous study, with the help of piezoelectricity relationships and the elastic energy formula, the Monte Carlo N‐Particle eXtended (MCNPX) simulation code was applied to find the amount of created atomic/nuclear particles, the dominant interactions; and the energy of the particles for various sizes of quartz and granite blocks. In this study, using the MCNPX simulation code, we have estimated the flux of the particles (created from under-stressed granitic rocks) at different distances from the EQ hypocenter inside the fractures, filled with air, water, and CO2. It was found that inside a water-filled fracture, the particles do not show the flux far from the EQ hypocenter. However, inside the gases like air and CO2 with the normal condition density, different types of particles can have a flux far from the source (more than a kilometer) and they might reach themselves to the surface in the case that the EQ hypocenter is very shallow (0­-5 km). However, for deep EQs, it seems that the most detected nuclear particles on the surface should pass via the vacuum-filled fractures and reach the surface. Moreover, it was concluded that the higher the density of the fracture’s filling fluid, the less distance that the particles can have a flux. National Research and Innovation Agency 2024-02-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1311 10.55981/aij.2024.1311 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 27-35 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1311/1108 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2249 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2250 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2252 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2383 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2384 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2385 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2386 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2389 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1311/2390 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1052 2021-09-16T00:51:46Z aij:ART

Estimation of Population Size and Dispersal Pattern of Sterile Male Aedes aegypti Using Mark-Release-Recapture (MRR) Technique Zulfa, R. Yuliawati, S. Martini, M. Hestiningsih, R. Ernawan, B. Sterile Insect Technique (SIT); Rhodamine-B; Ae. aegypti; Mark-Release-Recapture (MRR) Aedes aegypti is currently emerging as a main vector of Dengue, Zika, and Chikungunya transmission. Chemical control was reported to be less effective due to the resistance of this mosquito to some types of insecticides. Therefore, another vector control is needed which is most appropriate to be used, i.e. the sterile insect technique (SIT). Information about optimum range dispersal sterile male Aedes aegypti for optimalization SIT program are needed. This study was designed to determine the dispersal pattern and population estimation of Aedes aegypti sterilized with gamma rays using mark-release-recapture (MRR) method. After the male Aedes aegypti (pupal stage) was irradiated with 70 Gy of gamma rays, the mosquitoes were then marked with Rhodamine-B and released into the study site. MRR experiments were carried out in Batan Indah residential area, and the Aedes aegypti were released in center of the site. Mosquitoes were recaptured at 28 points spread over the Batan Indah Residence for 2, 4, 6, and 8 days after release by using BG-Sentinel Traps. The result showed that the population of Aedes aegypti in the site was estimated to be 5.402 (1.347–14.636; CI 95 %) with the furthest spread distance was 119 meters from the release point. This study also showed that the MRR experiment can be used to estimate the population size and dispersal pattern of Aedes aegypti movement in a given locality. The result of present study provide better understanding for optimalization mosquito-borne disease prevention based on SIT programs. National Research and Innovation Agency Martini Martini, Sri Yuliawati, Retno Hestiningsih, Public Health Faculty of Diponegoro University Beni Ernawan, Center for Isotopes and Radiation Application, National Nuclear Energy Agency 2021-07-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1052 10.17146/aij.2021.1052 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 93-98 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1052/978 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1793 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1798 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1870 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1871 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1872 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1873 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1052/1874 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1421 2024-12-13T01:11:07Z aij:ART

The Impact of Different Light-Reflecting Materials Compositions of (LaBr3:Ce) Scintillation Detector on Spent Nuclear Fuel Gamma Spectrum El-Tayebany, R. A. MCNPX, LaBr3(Ce) scintillators; Absolute efficiency; Light-reflecting materials; Gamma-ray The Scintillation detectors are extensively employed in nuclear safeguards, nuclear security fields, radioactive material testing, and physics research. Light-reflecting materials of (LaBr3:Ce) scintillation detectors positively affect their ability to capture light. Our goal is to investigate the characteristics of various reflectors by MCNPX code. In this paper, high-activity fission products from the spent fuel, identified as the utilized radionuclides 152Eu, 154Eu, 134Cs, 137Cs, and 243Cm, have been used in the simulation. Also, short-lived fission products, and short-lived actinides (239U and 239Np), which have decay heat in the timeframe of severe accident analysis, have been included. The findings of this investigation are consistent with the discovery that LaBr3:Ce delivers superior resolution. Additionally, some closely spaced peaks in the spectra of numerous radioisotopes could be resolved by the LaBr3:Ce detector. With different energy lines, the spectral responses of the scintillators' various reflectors were evaluated. National Research and Innovation Agency 2024-09-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1421 10.55981/aij.2024.1421 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 213-219 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1421/1133 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1421/2520 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1421/2521 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1421/2522 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1421/2602 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1114 2022-04-12T07:23:13Z aij:ART

Correlations Between Body Weight and Size-Specific Dose Estimate on Thoracic Computed Tomography Examination Wati, A. L. Anam, C. Nitasari, A. Syarifudin, S Dougherty, G. CTDIvol; SSDE; Body weight; Water-equivalent diameter; CT thorax The dose received by a patient on CT examination is expressed in size-specific dose estimates (SSDE) which is a function of the patient diameter, x-ray attenuation, and scanner output (volume computed tomography dose index, CTDIvol). Patient diameter and x-ray attenuation are represented as water equivalent diameter (Dw). We conducted the research to analyze the relationships between body weight and Dw, CTDIvol, and size-specific dose estimates (SSDE) in contrast-enhanced thorax examinations. We used images from 100 patients (50 women and 50 men patients) whose weight range from 2.8 kg to 80 kg. The values of Dw, CTDIvol, and SSDE were automatically calculated from axial CT images using the IndoseCT software. Statistical analysis showed that the patient's body weight correlates linearly with the Dw. The linearity coefficient (R2) values for body weight and Dw is 0.43 (women) and 0.55 (men). However, weight was independent of the patient dose in terms of CTDIvol and SSDE. This was because the CT system used tube current modulation (TCM), which automatically adapted the tube current to patient size, resulting in a relatively constant dose regardless of the patient size (Dw). National Research and Innovation Agency Riset Publikasi Internasional Bereputasi Tiggi (RPIBT), Diponegoro University. 2022-04-06 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1114 10.17146/aij.2022.1114 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 61-65 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1114/1011 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1114/1911 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1114/2094 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1596 2025-08-07T00:44:56Z aij:ART

Seismic Risk Analysis of the Serpong Nuclear Complex and the RSG-GAS Reactor Using Microseismic Methods Satriyo, A. Suryanto, W. Anggono, T. Subekti, M. Sucipta, S Jatnika, J. Swastikarani, R. Sugianto, N. Serpong Nuclear Complex (SNC); Reactor RSG-GAS; Horizontal to Vertical Spectral Ratio (HVSR); Floor Spectral Ratio (FSR); Peak Ground Acceleration (PGA) The G.A. Siwabessy research reactor (RSG-GAS), located in the Serpong Nuclear Complex (SNC), is a critical component of Indonesia's nuclear research infrastructure. This study aims to assess the seismic safety of the RSG-GAS reactor and its surrounding complex using microseismic methods, specifically the Horizontal-to-Vertical Spectral Ratio (HVSR) and Floor Spectral Ratio (FSR) techniques. HVSR measurements conducted across the B. J. Habibie Science and Technology Area (KST) revealed an average natural frequency (f₀) of 3.49 Hz (range: 2.84-4.43 Hz), amplification factors (A₀) averaging 2.84 (range: 2.11-4.88), and seismic susceptibility indices (Kg) averaging 2.72 (range: 1.34-4.39). The HK9 site, positioned 124 meters from the reactor, exhibited lower-than-average values, indicating reduced seismic vulnerability in the immediate reactor vicinity. FSR analysis was conducted to evaluate key structural parameters, including the Resonance Index (IR), inter-level deviation (γⱼ), peak ground acceleration (αbⱼ), and Building Vulnerability Index (Ktgⱼ). Most IR values fell within the medium-risk range (20.07 %-22.63 %), while one measurement point recorded 3.98 %, indicating high resonance risk. Inter-level deviations remained within acceptable safety thresholds; however, peak ground acceleration values exceeded critical limits at several levels, most notably at FU8 where 272.63 gal was recorded at -6.5 m elevation-significantly surpassing established safety standards. Several Building Vulnerability Index values also exceeded recommended safety limits. The findings demonstrate that while the RSG-GAS facility generally exhibits low-to-moderate seismic amplification and structural vulnerability, targeted structural reinforcements are essential at critical locations, particularly at the FU8 level. This study provides a comprehensive framework for enhancing seismic resilience of nuclear facilities in seismically active regions and contributes to the long-term safety assessment protocols for Indonesia's nuclear infrastructure. National Research and Innovation Agency DBR BRIN 2025-07-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1596 10.55981/aij.2025.1596 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 145-163 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1596/1175 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2610 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2743 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2744 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2745 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2746 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1596/2748 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1196 2023-06-03T02:55:28Z aij:ART

Dose Planning Evaluation of Intensity-Modulated Proton Therapy (IMPT) Technique Based on In-House Dynamic Thorax Phantom Vernanda, V. Azzi, A. Pawiro, S. A. Lung Cancer, IMPT, Planning, Bragg-peak, IMRT One of the drawbacks of the Intensity Modulated Radiation Therapy (IMRT) technique is that the absorbed dose in healthy tissue is relatively high. Proton beam has characteristics that can compensate for these drawbacks. The Bragg peak characteristic of a proton beam allows the administration of high radiation doses to the target organ only. Non-Small Cell Lung Cancer (NSCLC) cases are located in the vicinity of many vital organs, so radiation doses that exceed a certain limit will have a significant impact on these organs. Proton is a heavy particle that exhibits interaction patterns with tissue heterogeneity that differ from that of photon. This study aims to determine the distribution of proton beam planning doses in the NSCLC cases with the Intensity Modulated Proton Therapy (IMPT) technique and compare its effectiveness with the IMRT technique. Treatment planning was done by using TPS Eclipse on the water phantom and on the in-house thorax dynamic phantom. The water phantom planning parameters used are one field at 0° and three fields at 45°, 135°, and 225°. In this study, a single, sum, and multiple field techniques on the in-house thorax dynamic phantom were used. The evaluation was performed by calculating Conformity Index (CI), Homogeneity Index (HI), and Gradient Index (GI) parameters for each treatment planning. As a result, a bit of difference in the CI the HI values are shown between IMPT and IMRT planning. The GI values of IMPT planning are in the range between 4.15-4.53, while the GI value of IMRT is 7.89. The histogram results of the planar dose distribution show that the IMPT treatment planning provides fewer off-target organ doses than the IMRT planning. Evaluation was also carried out on the    IMPT treatment planning of target organs in five areas of interest and four OAR positions. The evaluation results were then compared with the IMRT measurement data. As a result, the value of the point doses at the target organ      did not differ significantly. However, the absorbed dose with the IMPT technique at four OAR positions is nearly zero, which had a large difference compared to the IMRT technique. National Research and Innovation Agency 2023-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1196 10.55981/aij.2023.1196 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 7-11 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1196/1057 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1196/2263 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1196/2264 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1196/2265 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1196/2266 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1196/2280 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1957 2026-04-06T04:44:45Z aij:ACKv51no3

Acknowledgement Atom Indonesia Vol 52 No 1 Indonesia, Atom National Research and Innovation Agency 2026-02-26 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1957 10.55981/aij.2026.1957 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1957/1214 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/995 2020-12-29T20:41:38Z aij:ART

Natural Radionuclides Determination and Radiological Hazard Assessments in Soil from Tual and Kei Islands, Indonesia Syarbaini, S Kusdiana, K Wiyono, M. Iskandar, D. Soil; Natural radioactivity; Gamma spectrometry; Radiological hazards Natural radionuclides 226Ra, 232Th and 40K in soil are the primary component of the background exposure sources of the population. Study of the external exposure due to gamma-ray radiation of natural radionuclides is important because this may contribute significantly to the total annual individual dose. The purpose of this   study is to investigate the natural radionuclides in soils collected from Tual and Kei islands and assess the radiological hazard due to natural radionuclides contents in soil. The soil samples were analyzed for natural radionuclides 226Ra, 232Th and 40K using gamma ray spectrometry. Radiological hazard parameters were estimated from the activity concentration of these radionuclides in order to assess health implication of exposure of the general public. The activity concentrations of 226Ra, 232Th and 40K in soil samples varied from 7.50 Bq kg-1 to 6326 Bq kg-1, 0.99 Bq kg-1 to 157 Bq kg-1, 2.97 kg-1to 98.91 Bq kg-1 with the average value of 2162 Bq kg-1; 69.68 Bq kg-1 and 30.74 Bq kg-1, respectively. The absorbed dose rates due to the presence of 226Ra, 232Th and 40K, in soil samples in the studied area vary between the range of 4.88 nGy h-1 and 3018.80 nGy h-1 with the average value of 1042 nGy h-1. The corresponding outdoor annual effective doses ranged between 0.01 mSv y-1 and 3.70 mSv y-1 with the average value of 1.28 mSv y-1. Radium equivalent activities are calculated to be in the range of 10.42 Bq kg-1 -6553.03 Bq kg-1 with the average value of 2264 Bq kg-1.The external and internal hazard indexes vary from 0.03 to 17.71 with the average value of 6.12 and 0.05 to 34.81 with the average value of 11.96, respectively. All calculated average radiological hazard indices were higher than the limits recommended for individual members of the public. National Research and Innovation Agency 2020-08-21 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/995 10.17146/aij.2020.995 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 99-105 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/995/842 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1608 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1615 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1685 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1754 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1846 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1847 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1848 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/995/1849 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1187 2023-12-19T03:11:18Z aij:ART

Analytical Studies on the Radionuclide Levels of Sediment and Water in an Agricultural Environment in the Egyptian Delta Shady, R. A. Elzain, A. E. Total Organic Matter (TOM) content; Activity concentrations; Total Dissolved Solids (TDS); Heavy metals This paper is an environmental investigation of the concentration values of radioisotopes and hazardous elements, aimed to shed light on industrial pollution and the effect of using fertilizers in the period of irrigation water drainage from cultivated lands, especially in the River Nile, irrigated, and draining channels in the middle portion of the Egyptian river delta. Different samples were analyzed, both for water and sediment. Many physical and chemical characteristics of samples were investigated. Among them are the quantitative measure of the acidity or basicity of aqueous or other liquid solutions (pH), grain size, and the total organic matter content (TOM) have been determined for sediments. pH and TDS, beside other types of pollutants, were determined for water samples. The water and sediment samples pH are slightly alkaline. The mean value of TDS for water samples is 488 mg/l, while he usual TDS value in river is 500 mg/l. The TOM values show that the sediment samples are poor in organic matter content. The bicarbonate range in the water samples is smaller than the same range in river water. The levels of Ra-226, Th-232, and K-40 activity in sediments are highly correlated. Natural radionuclides seem to correlate with the artificial Cs-137 in sediment. For this peruse, a 240 cm3 high-purity germanium reagent Type-B was used to quantify the levels in each sample with a relative accuracy of 50 %. The radioactive element K-40 is having a typical value of 12.5 Bq/kg. The concentrations of both Cu beside Zn in water samples is smaller if compared with values that quoted by the WHO, the US-EPA, and the EC. It was also found that the average levels for both Cd and Mn are found to be close to the internationally recommended levels. The water and sediments in the southern part of the canal contain higher concentrations of heavy metals and radioactive isotopes than in the rest of the canal. National Research and Innovation Agency The author declare no conflict of interest I am gratefully thankful to Tanta university, Egypt, for provided facilities 2023-12-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1187 10.55981/aij.2023.1187 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 201-208 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1187/1097 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1187/2051 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1423 2024-09-10T08:58:51Z aij:ART

Evaluation of Tumor Control Probability and Normal Tissue Complication Probability of Breast Cancer Treatment Plan in Post Mastectomy Radiation Therapy Herwiningsih, S. Yuana, F. Latifah, R. Hidayat, A. Rahmahtullah, D. P. Alviani, I. Hentihu, F. K. Breast cancer; Normal tissue complication probability; post mastectomy; Radiation Therapy; Tumor Control Probability Radiotherapy has been widely used to treat cancer, including breast cancer treatment, which can be given after patients undergo mastectomy procedures. This study aims to evaluate tumor control probability (TCP) and normal tissue complication probability (NTCP) of three-dimensional conformal radiation therapy (3DCRT) and intensity modulated radiation therapy (IMRT) treatment planning in post-mastectomy breast cancer radiation therapy. Twenty clinical breast cancer treatment plans delivered using 3DCRT were evaluated retrospectively. The IMRT plans were created for the same patients. The dose-volume histograms of each plan were extracted from the Treatment Planning System (TPS) computer which were then used to compute the TCP and NTCP for each plan. The TCP was calculated using the Poisson model and the NTCP was calculated using the Lyman-Kutcher-Burman (LKB) model. The NTCP was calculated for normal lung tissue, heart, esophagus, and spinal cord. The results show that the TCP of the 3DCRT and IMRT plans are not significantly different, with a value of above 99 %. The NTCP of the left lung is lower in the IMRT plans while the NTCP of the esophagus is lower in the 3DCRT plans. The NTCP for the heart, spinal cord, and right normal lung are zero in all plans. National Research and Innovation Agency Faculty of Mathematics and Natural Sciences, Universitas Brawijaya 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1423 10.55981/aij.2024.1423 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 159-164 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1423/1124 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2454 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2502 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2465 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2466 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2467 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2468 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2503 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1423/2504 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1206 2021-12-13T13:24:41Z aij:ACKv47no3

Acknowledgement Atom Indonesia Vol 47 No 3 ack47no3, ack47no3 National Research and Innovation Agency 2021-08-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1206 10.17146/aij.2021.1206 Atom Indonesia; Vol 47, No 3 (2021): December 2021 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1206/1002 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1659 2025-04-14T03:30:31Z aij:CVRv51no1

Cover Atom Indonesia Vol 51 No 1 indonesia, atom National Research and Innovation Agency 2024-12-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1659 10.55981/aij.2025.1659 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1659/1166 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1227 2022-12-22T17:40:30Z aij:ART

Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh Zihan, K. M. Z. Hoq, M. A. Khaer, M. A. Chowdhury, M. T. Rahman, M. M. Islam, M. S. Rahman, M. M. Radiological Dose; Immersion; Ground Deposition; Gaussian Diffusion Factor; Safety. Radiological dose distribution owing to the deposition of 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe on ground and immersion considering a postulated accident of TRIGA Mark-II research reactor has been assessed. The radiological dose distribution has been carried out in various directions with the help of Gaussian Diffusion Model. Local meteorological data such as average wind speed, frequency, etc. has been collected and evaluated for various directions around the reactor site. For all the dominant directions, the maximum dose values due to 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, 138Xe and the total (131mXe + 133mXe + 133Xe + 135mXe + 135Xe + 138Xe) were observed within the limit 3.03E-7–1.23E-4 µSv/h, 1.01E-5–4.09E-3 µSv/h, 0.0003–0.14 µSv/h, 2.29E-5–9.26E-3 µSv/h, 0.002 –1.111 µSv/h, 1.11E-5–4.55E-3 µSv/h, and 0.003–1.269 µSv/h, respectively. Dose distribution was found to be dominant due to immersion and the contribution was 87.55 %. There is shortage of data regarding the release of radioxenon in the atmosphere during nuclear accident especially in the case of TRIGA type research reactor. This paper is the first such detailed study on atmospheric release of radioxenon and its dose distribution for a full power- reactor and the consequences towards the environment and public health. The result can be applied to develop the radiological protective measures and to prepare an emergency response plan for the TRIGA reactor site. National Research and Innovation Agency Ministry of Science and Technology, Government of the People’s Republic of Bangladesh 2022-12-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1227 10.17146/aij.2022.1227 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 215-223 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1227/1049 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1227/2202 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1227/2203 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1227/2204 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1227/2205 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1676 2026-04-09T04:15:43Z aij:ART

Probabilistic Model of Liquefaction in Serpong and Its Impact on Nuclear Installation Safety Haifani, A. M. Prakoso, W. Setiadipura, T. Suntoko, H. Muhammad, A. G. Nuclear Power Plant; Liquefaction hazard analysis; cyclic stress ratio; probabilistic model This study delivers the first full probabilistic liquefaction hazard assessment specifically for an Indonesian nuclear power station (NPP) site, filling a major gap in current geotechnical risk evaluation techniques for nuclear infrastructure. We want to assess liquefaction risk under seismic loading in the Serpong region, a potential site for future NPP development, by integrating seismic hazard data and geotechnical site characteristics. The technique includes Probabilistic Seismic Hazard Analysis (PSHA), Ground Motion Prediction Equations (GMPEs), disaggregation curves, and soil characteristics extracted from 18 boreholes, such as SPT-N values, fines content, and groundwater level changes. Liquefaction triggering is assessed using Cyclic Stress Ratio (CSR), Cyclic Resistance Ratio (CRR), and associated factors (MSF, Rd), followed by probabilistic validation. Over a 50-year exposure period, the total liquefaction probability ranges from 0.5676 to 0.594, with the maximum vulnerability seen in water-saturated sandy layers at depths of 1-6 meters. These findings emphasize localized seismic susceptibility and have direct implications for risk-informed NPP foundation design and regulatory safety evaluations. Furthermore, the findings can be integrated into Probabilistic Safety Assessment (PSA) frameworks to help with quantitative risk indicators like Core Damage Frequency (CDF) and Large Early Release Frequency (LERF). This study provides a reproducible methodology for assessing liquefaction at nuclear plants in other seismically active regions. National Research and Innovation Agency National Research and Innovation Agency 2026-03-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1676 10.55981/aij.2026.1676 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 29-42 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1676/1205 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1676/2911 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1676/2912 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1676/2913 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1676/2914 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1676/2915 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1334 2023-06-03T02:55:28Z aij:PRVv49no1

oai:ojs.aij.batan.go.id:article/1366 2023-08-29T08:25:55Z aij:PRVv49no2

Preface Atom Indonesia Vol 49 No 2 prfc49no2, prfc49no2 National Research and Innovation Agency 2023-05-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1366 10.55981/aij.2023.1366 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1366/1088 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1005 2021-06-28T15:53:36Z aij:ART

Conceptual Design of Experimental Facility for Large-Diameter NTD-Si at the IRT-T Reactor Lebedev, I. I. Zolotykh, D. E. Naymushin, A. G. Smolnikov, N. V. Anikin, M. N. Varlachev, V. V. Neutron transmutation doping of silicon; NTD-Si; Thermal neutron filter; Research reactor IRT-T; Neutron flux profile The IRT-T reactor has been conducting research in the field of irradiation of ingots of single-crystal semiconductor materials since 1987. The article describes the existing silicon doping facility. The results of studies on the possibility of creating an additional irradiation channel for neutron-transmutation doping of silicon are presented. It is shown that the use of a graphite reflector and a thermal neutron filter based on boron makes it possible to achieve non-uniformity of irradiation up to 5 %. The principal possibility of irradiating single-crystal silicon ingots with a diameter of up to 203 mm and a length of up to 500 mm is shown. The questions of optimizing the configuration of the core and the regime of reactors operation for increasing the neutron flux in the irradiation channels are discussed. In addition, applying the facility to produce base materials for neutron dosimeter in neutron capture therapy studies is proposed. National Research and Innovation Agency Tomsk Polytechnic University CE Program grant 2021-04-12 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1005 10.17146/aij.2021.1005 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 39-44 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1005/894 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1709 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1712 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1974 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1975 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1976 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1005/1977 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1381 2024-04-05T22:38:53Z aij:ART

The Effect of I-131 Treatment on Complete Blood Count Sahutoglu, G. Cetin, S. K. Atilgan, H. I. Thyroid cancer; Iodine-131; Hemoglobin; Leukocyte; Thrombocyte Radioactive iodine-131 (RAI) treatment may cause suppression in the bone marrow. In this study, hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts will be compared before total thyroidectomy and 6 months after RAI treatment. 97 patients (76 females, 21 males) with a diagnosis of    well-differentiated thyroid cancer who had undergone total thyroidectomy and received 50-200 mCi RAI treatment were included in the study. Hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts of the patients in the last month before the treatment and in the sixth month after the treatment were compared retrospectively. When the whole patients were analyzed, hemoglobin levels, leukocyte, thrombocyte, and lymphocyte counts in pretreatment were statistically lower than after-treatment values. While hemoglobin levels of female patients were similar before and after treatment, lymphocyte, thrombocyte, and leukocyte counts were statistically lower before treatment. Hemoglobin levels, leukocyte,and thrombocyte counts were similar before and after treatment, while lymphocytes decreased significantly after RAI treatment. Thyroid cancer patients who received 50-200 mCi RAI treatment after total thyroidectomy, have bone marrow suppression but are still in normal mean value ranges. This mild bone marrow suppression is more prominent in female patients than in male patients. National Research and Innovation Agency 2024-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1381 10.55981/aij.2024.1381 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 67-70 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1381/1114 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1381/2403 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1381/2404 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1381/2405 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1381/2406 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1381/2412 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1041 2021-12-09T05:39:37Z aij:ART

Implementation of Beam Matching Concept for the New Installed Elekta Precise Treatment System Medical LINACs in Indonesia Firmansyah, O. A. Firmansyah, A. F. Sunaryati, S. I. Putri, M. M. Setiadi, A. R. Akbar, O. A. Arif, V. Amelia, C. Beam matching; PDD; Profile; Linac A concept of radiation beam matching of some medical linear accelerators (LINACs) that have identical characteristics of the models, radiation quality, and multileaf collimator features may be implemented as long as the manufacturer provides complete specifications so that a Treatment Planning System (TPS) can be used for many beam-matched LINACs. This paper describes a preliminary study on the implementation of the beam matching concept for five units Elekta Precise Treatment System LINACs that have recently been installed in Indonesia. The beam matching criteria were based on the percentage depth dose (PDD) and beam profile for photon and electron beams. Dosimetry measurements were carried out by using an SNC 125 ionization chamber of 0.125 cm3 in volume, PTW Pinpoint 3D of  0.016 cm3 in volume, and PTW Farmer Chamber of 0.6 cm3 in volume. The results indicated that the PDD10 of 6 and 10 MV photon beams among installed five units LINACs have excellent compatibility each others with a maximum deviation of less than 0.4 %, while the maximum deviation for dose depth of 80 % (R80) for the electron beams with nominal energies of 4, 6, 8, 10, 15 and 18 MeV is 1 mm. The measurement results for the flatness profile were less than 6 %, and symmetry profiles were less than 3 %. It also outlines the determination of the absorbed dose to water under reference conditions. The results of the calibration of output doses show that the absorbed dose in the water was 1 cGy ≈ 1 MU. The data obtained from measurements for each LINAC conform with the requirements of the beam matching process set by the manufacturer. National Research and Innovation Agency Center for safety technology and radiation metrology, Sanglah Central General Hospital Denpasar Bali, Central General Hospital Dr. Mohammad Hoesin Palembang, Persahabatan Hospital Jakarta, Dr. Hasan Sadikin Bandung, Hospital Dr. Adam Malik Medan 2021-11-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1041 10.17146/aij.2021.1041 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 181-189 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1041/988 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/1797 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/2066 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/2067 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/2068 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/2069 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1041/2070 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1401 2025-04-14T03:30:31Z aij:ART

Source Identification Performance of Plastic Scintillator Ranging from 100–1300 keV: Assessment Through Monte Carlo Code and Experimental Validation Putro, G. E. Omar, M. R. Kasmudin, K. Nuri, H. L. Pancoko, M. Jamil, A. Subhiyah, H. Gamma detector; Monte Carlo; Experimental; Efficiency; Resolution Current plastic detectors need improvement in efficiency and accuracy, to enhance reliability. Simulation offers a cost-effective approach to accelerate detector development, yet its effectiveness relies on the reliability of the simulations used. Therefore, validating these simulations is crucial to ensure they accurately reflect actual scenarios and yield reliable results. This study employs the Monte Carlo approach to estimate the performance and efficiency of a plastic detector exposed to radiation sources within the 100–1300 keV energy range. The plastic detector (50 mm x 3 mm) was simulated using MCNP with Gaussian Energy Broadening (GEB) correction applied to capture detector response. Simulated data were then compared against experimental measurements to validate the model. This work aims to confirm that simulation results align with empirical data, ensuring theoretical models accurately represent physical phenomena. The study highlights both the limitations and strengths of simulation codes, leading to more efficient research through validated models. Notably, an 8.04 % deviation was observed at 662 keV for 137Cs, demonstrating a strong correlation between simulated and experimental results and confirming the model’s accuracy and reliability. National Research and Innovation Agency Research Organization for Nuclear Energy (ORTN BRIN) 2025-02-12 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1401 10.55981/aij.2025.1401 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 11-26 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1401/1151 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2541 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2542 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2543 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2544 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2545 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2632 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1401/2633 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1131 2022-08-22T00:27:11Z aij:ART

The Establishment of Institutional Diagnostic Reference Levels (DRLs) in the Cipto Mangunkusumo Hospital Amalia, T. Zulkarnaien, B. Anam, C. Nurcahyo, K. Tussyadiah, H. Pradana, D. E. Diagnostic reference levels; Diagnostic radiology; Optimization; Patient safety Institutional diagnostic reference levels are used for quality assurance in radiology departments. The purpose of this study was to establish an institutional diagnostic reference level (DRL) and to provide a practical tool in diagnostic radiology and nuclear medicine. For each type of procedure/examination, it needs at least 20 patients. The patients with regular size (average body size is 65 ± 10 kg for adult patients and 15±15 kg for pediatric patients) were enrolled in this project. The 75 percentile values of doses were used as institutional DRLs.  For nuclear medicine, the administered activities was based on the dose of activity to produce a good image. The DRL values were obtained for general radiography, nuclear medicine, mammography, CT examination, and interventional radiography. The DRL's result was compared to national DRL (NDRL) and values in other countries. The DRL values for general radiography in this study are higher compared to NDRL and Japanese study. The administered activities (MBq) for nuclear medicine in this study are higher compared to European Commission but lower when compared to a Japanese study. The DRL values for mammography in this study are higher compared to ARPANSA; however, they are lower than NDRL and UK studies. The DRL values for CT examination in this study are higher compared to Netherland, Canadian, and USA studies but lower than NDRL. The DRL values in interventional radiography (IR) in this study are lower compared to the IAEA study. This finding indicates that it is still necessary to optimize procedures in the future. The established institutional DRL values can be used as a tool for optimization. National Research and Innovation Agency Installation of Radiology and Nuclear Medicine, dr. Cipto Mangunkusumo Hospital, Jakarta, Indonesia 2022-08-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1131 10.17146/aij.2022.1131 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 159-167 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1131/1028 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1131/1955 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1628 2026-02-26T03:01:50Z aij:ART

Characterization and Sorption Study of Cesium-137 by Bentonite from Santrijaya, Indonesia as an Engineering Barrier Material for Radioactive Waste Disposal Facilities Sriwahyuni, H. Krisnandi, Y. K. Basuki, T. Setiawan, B. Budianti, A. Anggraini, Z. Nurliati, G. Pamungkas, N. S. Sorption; Cesium; Bentonite; Engineered barrier; Disposal facilities; Radioactive waste Engineered barrier materials, such as bentonite, play a critical role for the safety of radioactive waste disposal systems by limiting radionuclide migration. This study aims to evaluate the mineralogical, chemical, and morphological characteristics of natural bentonite from Santrijaya, Tasikmalaya, Indonesia, and to investigate its Cs-137 sorption behavior, focusing on its potential as a candidate for engineered barrier materials. X-Ray Diffraction (XRD) and X-Ray Fluorescence (XRF) analyses showed that the bentonite predominantly consists of montmorillonite, with silica contributing about 80 percent of its composition. The material shows a specific surface area of 121.89 m²/g and a cation exchange capacity of 43.23 meq/100g, supporting its suitability for radionuclide sorption. The sorption capacity at equilibrium (q_e) achieved at 536.67 mg-Cesium/g-bentonite after 10 days of contact time, with adsorption kinetics that follows the Pseudo-Second Order (PSO) model and the distribution coefficient (K_d) value of 5211 mL/g. The study shows the competitive effects of K+ and Na+ ions, with K+ ions showing a stronger competitiveness for Cs-137 binding sites than that of Na+, which could influence radionuclide retention. These findings highlight the high sorption efficiency and stability of Santrijaya bentonite, showing its potential as a barrier material for radioactive waste containment systems and suggest the necessity of considering competing ion interactions in the design of barrier materials. National Research and Innovation Agency Heru Sriwahyuni, Triyono Basuki, Budi Setiawan, Niken Siwi Pamungkas, Zeni Anggraini, Arie Budiantie National Research and Innovation Agency, Yuni K Krisnandi Departement of Chemistry Universitas Indonesia, Niken Siwi P Radionuke Consultant Indonesia 2025-12-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1628 10.55981/aij.2025.1628 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 249-257 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1628/1196 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1628/2864 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1628/2865 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1628/2866 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1628/2867 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1219 2023-08-29T02:15:31Z aij:ART

Optimizing Neutronic and Photonic Performance in Irradiation Systems of Symmetric TRIGA Cores Shauddin, S. M. Beam-port, Gamma photon flux, Irradiation system, TRIGA, MCNP The BAEC TRIGA MARK-II Research Reactor (BTRR) in Bangladesh has been used for a wide range of purposes, including basic and applied nuclear research and human resource development. Therefore, its core management should be flexible to meet various objectives with different priorities and to deliver the best possible outcome. In this study, neutron and gamma photon flux variation was studied at different radial and axial irradiation systems of the current core (C-0) as well as six symmetric reconfigurations (C-1, C-2, C-3, C-4, C-5, and C-6) of the existing BTRR using the universal MCNP code. While keeping the exact core component and material density, the symmetric reconfigured cores were modeled based on core criticality calculation and excess reactivity in the critical state. Finally, it was observed that the reconfigured core C-1 has the best neutronic and photonic performance at the irradiation systems compared to other reconfigured cores, against the reference core C-0. National Research and Innovation Agency 2023-07-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1219 10.55981/aij.2023.1219 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 89-95 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1219/1078 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1219/2297 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1219/2318 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1219/2319 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1219/2320 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1219/2321 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1107 2020-12-23T05:14:08Z aij:CVRv46no3

Cover Atom Indonesia Vol 46 No 3 cvr46no3, cvr46no3 National Research and Innovation Agency 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1107 10.17146/aij.2020.1107 Atom Indonesia; Vol 46, No 3 (2020): December 2020 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1107/870 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1033 2021-08-30T07:42:43Z aij:ART

Addition of Lead (Pb)-Nitrate Filler on Polymer Composite Aprons for X-Ray Radiation Shielding Afrianti, E. Tahir, D. Jumpeno, B. Y. E. B Firmansyah, O. A. Mellawati, J. Polymer Apron; Filler; Pb-nitrate; Effectiveness; Tensile Strength Radiation shielding aprons are needed by radiation workers to minimize radiation exposure to the body. The aprons at present use fabric-coated lead plates which are heavy and rigid materials and therefore are not comfortable to use. Polymer aprons from cassava starch and glycerin with addition of Pb-nitrate filler at 0 %, 2 %, 4 %, and 6 % have been synthesized. Mixtures for synthesizing the polymer apron composites were heated using a magnetic stirrer at a speed of 800 rpm at 160 °C for 25 minutes. Then, the polymer apron composites were dried in an oven for 24 hours at 70 °C. The effectiveness of the apron was determined by calculating the attenuation coefficient (μ), half-value layer (HVL), and radiation absorption. The mechanical properties of the aprons were characterized by testing their tensile strengths using anAD MCT-2150 universal tester. The result shows that the optimal addition of Pb-nitrate filler of as much as 6 % produced aprons with an attenuation coefficient of 1248 cm‑1, HVL of 0.54 cm, and radiation absorption of 25 %, while the aprons’ tensile strength was obtained as28.244 MPa. The addition of Pb-nitrate as a filler in apron composites proportionally improves the quality of materials used as radiation shields. More detailed research is still needed to obtain the best apron. National Research and Innovation Agency 2021-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1033 10.17146/aij.2021.1033 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 129-133 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1033/983 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1033/1969 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1033/2044 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1033/2045 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1033/2046 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1033/2047 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1468 2024-12-03T02:00:49Z aij:ART

Ground-Based Gamma-Ray Spectrometer Application on Drone-Borne: Suitability and Height Attenuation Syaeful, H. Muhammad, A. G. Rachael, Y. Pratiwi, F. Rosianna, I. Ngadenin, N Indrastomo, F. D. Ciputra, R. C. Sukadana, I. G. Adimedha, T. B. Karunianto, A. J. Radiometric mapping; UAV; Drone; Uranium; Thorium; Spectrometer Rapid development in the use of unmanned aerial vehicles (UAVs) in many applications, such as topographic mapping, agricultural management, marine monitoring, and others, has also brought the radiometric mapping application to this drone-borne application. Before the application, several corrections are performed to the data, including stripping corrections obtained from calibration results and height attenuation corrections. This study aims to determine the effectiveness and the height attenuation of the ground-based spectrometer attached to the drone. The method is carried out to determine the optimal altitude and conduct direct testing in the field of a small detector of 0.1 l of RS-125 gamma-ray spectrometer using drone-borne radiometric applications. In ideal conditions without obstacles in the flying path, 15 m is considered the ideal height, proportional to the detector size. Based on the results of field measurements at a drone height of 24 m, the comparison of drone and ground data is acceptable for dose rate, thorium, and potassium concentration with Pearson correlation of 0.67, 0.49, and 0.45, respectively. The drone measurement result is less acceptable for uranium data, with a Pearson correlation of 0.05 to the ground measurement. In conclusion, the RS-125 gamma-ray spectrometer is generally suitable for drone-borne radiometric applications. National Research and Innovation Agency National Nuclear Energy Agency (BATAN) National Research and Innovation Agency (BRIN) 2024-11-21 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1468 10.55981/aij.2024.1468 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 259-265 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1468/1143 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2436 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2440 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2569 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2570 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2571 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2572 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1468/2578 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1188 2022-08-22T00:27:11Z aij:ART

Neutronic Evaluation of Using a Thorium Sulfate Solution in an Aqueous Homogeneous Reactor Pérez, D. Milian, D. Hernández, L. Gámez, A. Lorenzo, D. Brayner, C. 99Mo production; Aqueous Homogeneous Reactor; Thorium fuel; MCNP; fuel solution; Thorium Sulfate Radioisotope 99Mo is one of the most essential radioisotopes in nuclear medicine. Its production in an Aqueous Homogeneous Reactor (AHR) could be potentially advantageous compared to the traditional technology, based on target irradiation in a heterogeneous reactor. An AHR conceptual design using low-enriched uranium for the production of 99Mo has been studied in depth. So far, the possibility of replacing uranium with a non-uranium fuel, specifically a mixture of 232Th and 233U, has not been evaluated in the conceptual design. Therefore, the studies conducted in this article aim to evaluate the neutronic behavior of the AHR conceptual design using thorium sulfate solution. Here, the 232Th-233U composition to guarantee ten years of operation without refueling, conversion ratio, medical isotopes production levels, and reactor kinetic parameters were evaluated, using the computational code MCNP6. It was obtained that 14 % 233U enrichment guarantees the reactor operation for ten years without refueling. The conversion ratio was calculated at 0.14. The calculated 99Mo production in the AHR conceptual design resulted in 24.4 % higher with uranium fuel than with thorium fuel. National Research and Innovation Agency Coordination for the Improvement of Higher Education Personnel (CAPES) 2022-07-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1188 10.17146/aij.2022.1188 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 75-80 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1188/1019 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1188/2148 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1188/2149 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1188/2150 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1188/2151 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1188/2152 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1771 2025-08-07T00:44:56Z aij:ACKv51no2

Acknowledgement Atom Indonesia Vol 51 No 2 indonesia, atom National Research and Innovation Agency 2025-04-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1771 10.55981/aij.2025.1771 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 185 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1771/1183 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1226 2023-06-03T02:55:28Z aij:ART

Assessment of Health Risk of Exposure to Alpha-Emitters in Cheese Samples Collected from Iraqi Markets Muneam, R. R. Abojassim, A. A. Alpha-emitters; Health risk; CR-39 detector; Cheese samples; Iraqi markets In this research, alpha-emitter concentrations of 222Rn, 226Ra, and 238U in Iranian, Turkish, Egyptian, Saudi Arabian, and Iraqi canned cheeses that are available in Iraqi markets were measured using the CR-39 detector. Also, the health risk parameters associated with the ingestion of alpha-emitter radionuclides, such as the annual average internal effective dose (AAIED) and the risk of an excess cancer fatality per million persons (RECFPMP), were calculated. The results show that the average values of 222Rn, 226Ra, and 228U concentrations for all samples in the present study were 3.7±0.38 Bq/m3, 25.24±2.63 mBq/kg, and 0.025±0.002 ppm, respectively. The average values of AAIED and RECFPMP were 0.175±0.018 µSv/y and 0.674±0.070, respectively. The results show that the highest value of alpha-emitters as well as health risk parameters were found in cheese samples produced in Saudi Arabia, while the lowest results were found in Egyptian samples. They were, nevertheless, less than the permissible value and the risk value. According to the current study, the consumption of those cheese products poses no health risks. National Research and Innovation Agency 2023-04-06 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1226 10.55981/aij.2023.1226 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 39-44 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1226/1060 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2227 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2241 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2228 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2229 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2230 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1226/2254 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1092 2020-09-14T07:27:52Z aij:ACKv46no2

Acknowledgement Atom Indonesia Vol 46 No 2 ack, ack National Research and Innovation Agency 2020-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1092 10.17146/aij.2020.1092 Atom Indonesia; Vol 46, No 2 (2020): August 2020 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1092/848 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1405 2023-12-19T04:17:36Z aij:ACKv49no3

Acknowledgement Atom Indonesia Vol 49 No 3 ack48no3, ack48no3 Rohandi National Research and Innovation Agency 2023-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1405 10.55981/aij.2023.1405 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1405/1102 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1143 2021-06-28T15:53:36Z aij:PRVv47no1

Preface Atom Indonesia Vol 47 No 1 preface471, preface471 National Research and Innovation Agency 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1143 10.17146/aij.2021.1143 Atom Indonesia; Vol 47, No 1 (2021): April 2021 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1143/901 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1387 2024-09-10T08:58:51Z aij:ART

Non-Dimensional Number Analysis on Natural Circulation Flow Changes Inside Straight-Pipe Heat Exchanger of Water Cooling Tank in FASSIP-02 Test Loop Arista, E. P. Deendarlianto, D Al-amin, A. S. Setiawan, P. H. Gunawan, H. A. Juarsa, M. FASSIP-02; Non-dimensional; Straight-pipe; Natural circulation; Passive safety The FASSIP-02 test loop is a large-scale experimental facility that investigates natural circulation flow rate phenomena to improve passive safety systems of nuclear reactors. Heat transfer in the piping system will result in pattern and magnitude of the natural circulation flow being formed, so it is essential to investigate the heat dissipation capabilities, which will later be applied in nuclear passive cooling systems. The heat transfer behavior of passive cooling systems in large-scale facilities can be quantified with non-dimensional numbers. This research analyzes heat transfer in a straight heat exchanger by comparing non-dimensional numbers based on the Dittus-Boetler and McAdams correlation with the correlation generated from experimental data. The analysis results show that the predicted McAdams correlation with the experimental correlation is higher than 83 %. Meanwhile, Dittus Boetler's correlation prediction with the experimental correlation is smaller than 71 %. The dominance of momentum diffusivity in the cooling process shows the characteristics of thermal behavior with the Prandtl number. In addition, all-natural circulation flow variations occur in a turbulent flow regime that increases with increasing water temperature in the heating tank. National Research and Innovation Agency Mulya Juarsa, PRTRN ORTN BRIN 2024-08-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1387 10.55981/aij.2024.1387 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 201-210 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1387/1128 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1387/2476 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1387/2477 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1387/2478 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1387/2479 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1387/2480 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1190 2022-04-12T07:35:07Z aij:ART

Systematic Projected Shell Model Study of Even-Even Dysprosium Isotopes Aghahasani, H. Mohammadi, S. Sajjadi, Z. Projected Shell Model; Dysprosium isotopes; Electromagnetic transitions; Quadrupole moments Back-bending phenomenon is one of the important phenomena usually seen at high spin states of even - even heavy nuclei. As a result, any changes in the behavior of nuclear rotation, such as increase in moment of inertia versus rotational frequency can be shown in the usual back-bending plots which have been studied in many papers before. In this paper we show for the first time that these changes  can be seen in the  ratio of electromagnetic reduced transition probabilities B (E2) and B (M1) in even - even 152-164Dy isotopes using the Projected Shell Model (PSM) theory. The electric quadrupole transition probability B (E2) and the magnetic dipole transition probability B (M1) moments are sensitive to nuclear shape deformation and nuclear charge distribution, respectively. Our findings confirm the well-known back-bending previously seen and are in good agreement with experimental results. While intrinsic quadrupole moments are constant for each Dy isotope, the new findings show that spectroscopic quadrupole moments are increasing with spin. National Research and Innovation Agency N/A 2022-03-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1190 10.17146/aij.2022.1190 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 29-35 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1190/1010 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2055 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2137 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2138 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2139 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2140 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1190/2141 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1599 2025-08-07T00:44:56Z aij:ART

Dosimetric Evaluation of Very High Energy Electron (VHEE) Beams in the Male Pelvic Region Using Geant4/TOPAS Essaidi, E. M. Krim, M. Kaanouch, O. Tantaoui, M. Mesradi, M. R. Abdessamad, D. Benchekroun, D. Very High Energy Electrons (VHEE) Focused VHEE beams Collimated VHEE beams GEANT4/TOPAS Monte Carlo simulations Quadrupole magnets Radiological Protection. The CLEAR (CERN Linear Electron Accelerator for Research) facility has significantly advanced high-energy electron radiotherapy, particularly for treating deep-seated tumors. However, achieving precise and accessible treatment delivery while minimizing damage to surrounding healthy tissues remains challenging. Very High Energy Electrons Beam (VHEE) offer notable potential due to their deep penetration capabilities. However, their nearly uniform dose distribution raises concerns about unintended exposure to healthy tissues. A key innovation in this field is the use of focused VHEE beams, which deliver a concentrated dose to a small defined area at a high dose rate, potentially enhancing treatment precision. This study evaluates the dosimetric characteristics of focused VHEE beams compared to collimated beams using GEANT4/TOPAS Monte Carlo simulations. A beamline with two quadrupole magnet triplets was designed to focus VHEE beams on a water phantom, simulating clinical conditions. The findings show that focused VHEE beams increased the dose to the prostate by 5.24 % while significantly reducing the dose to adjacent organs at risk: 16.93 % to the bladder, 50.81 % to the rectum, and 68.75 % to the femoral heads. These reductions highlight the dosimetric advantage of focused VHEE beams in sparing non-targeted tissues. While these results underscore the potential benefits of focused VHEE beams for deep-seated tumor treatment, additional research, including clinical validation and patient-specific modeling, is essential to fully evaluate their clinical utility. This study lays the groundwork for optimizing VHEE beam applications in cancer therapy by demonstrating improved dose delivery accuracy and reduced risk to adjacent organs. National Research and Innovation Agency 2025-05-16 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1599 10.55981/aij.2025.1599 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 109-117 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1599/1170 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1599/2611 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1599/2694 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1599/2691 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1599/2692 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1599/2693 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1282 2022-12-23T13:43:43Z aij:CVRv48no3

Cover Atom Indonesia Vol 48 No 3 cover48no3, cover48no3 National Research and Innovation Agency 2022-11-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1282 10.17146/aij.2022.1282 Atom Indonesia; Vol 48, No 3 (2022): December 2022 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1282/1053 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1465 2026-04-07T05:11:04Z aij:ART

The Role of Neutron Absorbers in Soliton Wave Creation Using Heavy Water as a Diffusive Medium Shakeri, A. Abbasi, K. Hosseinimotlagh, S. N. Zarei, M. A. Rezaei, V. R. Bayat, J. Pour, A. G. Vanaie, H. R. Rasati, E. Burn; Soliton; Diffusive; Absorber; Flux One of the simplest nuclear fission reactor designs is the soliton reactor. In these reactors, neutrons reduce the toxicity of fissile materials in a manner that allows new vital areas appear successively. Therefore, the spatial dependence of the neutron flux, specific power density, and associated particle density exhibit wave phenomena of solitons and emerge from the solution of nonlinear partial differential equations, preserving their shape during propagation. The velocity of the burnup Soliton Wave (SW) is related to the density of the initial Nuclear Fuel (NF) in each Neutron Absorber (NA) in the medium. These nonlinear waves can be described by equations describing the atomic flux and density in terms of time and space in the medium. The soliton wave can also be observed in advanced nuclear power systems. Burnup SWs in a propagation medium can be analyzed using the spatial coordinates and position of the NA in a propagation region. The aim of this work is to investigate the burnup SW characteristics by selecting various isotopic neutron absorbers in the slab reactor core. Our computational findings show that the SW burning rate is affected by increasing the diffusion coefficient. However, both the diffusion length and the Length of Transient (LOT) increase with increasing the diffusion coefficient. Interestingly, the ratio of LOT to diffusion length remains constant. Furthermore, while increasing the diffusion coefficient leads to a higher Transient of Time (TOT), the ratio between TOT and characteristic time remains constant. National Research and Innovation Agency 2026-04-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1465 10.55981/aij.2026.1465 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 81-92 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1465/1212 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2435 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2437 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2793 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2794 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2916 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2908 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2909 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1465/2910 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1004 2020-09-25T01:26:18Z aij:ART

Construction and Evaluation of a Multipurpose Performance Check Phantom for Computed Tomography Lubis, L.E. Hariyati, I. Ryangga, D. Mu'minah, I.A.S. Mart, T. Soejoko, D.S. Computed tomography; Dose; Image quality; Phantom The use of computed tomography (CT) has become a common practice in medical diagnosis in Indonesia. Its number, however, is not matched by the availability of dedicated-performance-check phantoms. This paper aims to describe the design, construction, and evaluation of an in-house phantom for CT performance check that accommodates both radiation dose measurement and image quality performance checks. The phantom is designed as laser-cut polymethyl methacrylate (PMMA) slabs glued together to form a standard cylindrical shape, with spaces to place dose measurement and image quality modules. In this paper, measurement results on both aspects are discussed and compared with standard phantoms and other works. For dose measurement, the constructed phantom exhibited the greatest absolute discrepancy against the reference standard phantom of 8.89 %. Measurement of the CT number linearity and modulation transfer function (MTF) yielded, at most, 7.51 % and 5.07 % discrepancies against Catphan 604, respectively. Meanwhile, although found to be more linear in the phantom-based contrast linearity test, the use of the in-house phantom for clinical image contrast threshold determination requires further study. For noise power spectrum (NPS) measurement, accurate results were obtained within a limited range of spatial frequency. National Research and Innovation Agency Universitas Indonesia 2020-08-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1004 10.17146/aij.2020.1004 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 69-75 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1004/838 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1653 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1739 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1740 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1741 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1842 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1843 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1844 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1004/1845 Copyright (c) 2019 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1315 2023-12-19T03:11:18Z aij:ART

Evaluation of Changes in Dose Estimation on Abdomen CT Scan with Automatic Tube Current Modulation Using In-House Phantom Taopik, A. Lubis, L. E. Sihono, D. S. K. Soejoko, D. S. CT scan abdomen; ATCM; DRI; Pitch; In-house phantom This study evaluates the effect of the Automatic Tube Current Modulation (ATCM) technique on pitch and effective diameter variation in estimating dose values and noise levels for abdominal examination on Philips Ingenuity CT scan machine using in-house Phantoms. The in-house phantoms are oval in shape with three effective diameter sizes, namely 23.2 cm, 28.3 cm, and 33.3 cm to represent abdominal region. The three size Phantoms were scanned using an Ingenuity 128 Philips CT scan with the abdominal protocol exposure parameters of 120 kVp tube voltage, Dose Right Index (DRI) variations of 10,11,12,13, and 14, and pitch variations of 0.6; 0.8; 1.0; 1.2; and 1.49. The changes in mAs, CTDIvol, and noise to the Philips reference value were then verified (i.e. an addition of one DRI value increases mAs by 12 %). For evaluation, a metric to express the change in DRI is defined as ΔDRI. The study demonstrates that noise level is influenced by object size; size information of the object could be useful to predict the change of tube current and pitch due to ATCM with respect to selected DRI. The DRI value is proportional to the tube current, thus selecting the DRI at a certain pitch will directly determine tube current. The ΔDRI in general, according to Philips specifications, is verified to be approximately 10 % to 13 %, except for DRI 10 to 11 which is relatively high on average 15 % to 17 %. Increasing DRI increases the CTDIvol. The CTDI/mAs constantly ranges of 0.06 to 0.07. The value could serve as a characteristic parameter for quality assurance. The ATCM specifications of the Ingenuity 128 CT Scanner is according to Philips regulations. National Research and Innovation Agency 2023-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1315 10.55981/aij.2023.1315 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 169-175 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1315/1094 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1315/2350 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1315/2351 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1315/2352 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1315/2353 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1402 2024-09-10T08:58:51Z aij:ART

Radon Concentration in Biological Samples of Smokers and Non-smokers Using Lexan Detector Alkufi, A. A. Abojassim, A. A. Oleiwi, M. H. This study was conducted in the Najaf Governorate, Iraq, to analyze radon concentration in biological samples from smokers and non-smokers. The samples, including blood serum, urine, hair, and nails, were used as biomarkers to determine the presence or absence of radon (222Rn). Using a natural exposure method, the nuclear track detector (Lexan, Belgium) was utilized to measure these radon concentrations in the samples. Seventy-five samples of blood serum, urine, hair, and nails were collected for smokers of healthy people and fifty samples for non-smokers of healthy people in five age groups. This study was based on age and smoking to compare the results and determine their effects on radon concentrations. The results show that the average values of radon concentrations (in Bq/m3) in blood serum, urine, hair, and nails for smokers were 54.7 ± 22.1, 62.9 ± 23.1, 34.7 ± 11.2, and 41.7 ± 15.2, respectively. Meanwhile, the average values of radon concentrations (in Bq/m3) in blood serum, urine, hair, and nails for non-smokers were 24.2 ± 6.0, 30.0 ± 6.3, 18.7 ± 5.2, and 21.6 ± 6.9 respectively. The results and comparisons indicate that radon concentrations depend on the variables on which this study was based (age and smoking). Smokers and non-smokers had different levels of radon in all biological samples. The P-value was National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1402 10.55981/aij.2024.1402 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 127-134 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1402/1119 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1402/2492 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1402/2493 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1402/2494 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1402/2495 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1402/2496 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1130 2021-12-10T07:17:02Z aij:ART

Analysis of 137Cs Radionuclide Content in Sediment in Musi Watershed Using Gamma Spectrometer and its Affecting Factors Jaya, T. A. Mara, A. Amri, G. F. Radionuclide 137Cs, Gamma Spectrometer, Sediment The concentration of the radionuclide 137Cs on sediment in watershed in Palembang has been analyzed. This study aims to determine the influence of sampling location and the water quality indicators of water pH, sediment pH, conductivity, turbidity, and sediment type on the concentration of 137Cs and to determine the distribution pattern of 137Cs in sediments. Sampling was conducted at seven stations spaced approximately 5 km apart, placed from the western end to the eastern end  of the Musi river segment located within Palembang City.Sediment samples were prepared and their 137Cs contents were measured with gamma spectrometry. The results showed that their 137Cs concentrations ranged from below MDC (minimum detectable concentration) to 1.51 Bq/kg. This was within the 1×103 Bq/kg limit set by the quality standard. The varied and very low concentrations of 137Cs are thought to have originated from global fallout. The location point of sampling affects the concentration of radionuclide 137Cs while the characteristics of water quality are do not. The 137Cs concentration spread pattern in Musi sediment is influenced by tidal currents and river morphology. National Research and Innovation Agency National Nuclear Energy Agency 2021-12-03 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1130 10.17146/aij.2021.1130 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 219-226 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1130/991 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1130/1930 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1130/2085 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1130/2086 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1130/2087 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1130/2088 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1432 2025-04-14T03:30:31Z aij:ART

Customization of Source Term into JRODOS Compatible XML File Format Using Visual Basic for Nuclear Accident Analysis Hassan, S. M. T. Khaer, M. A. Hoq, M. A. Chowdhury, M. T. Rahman, M. M. JRODOS; Source Term; XML; Visual Basic; Radionuclide; Nuclear Accident Analysis A Visual Basic code was developed to generate an XML file in the RODOS format from the provided source term data in Microsoft Excel Spreadsheet. This XML file can be directly used in JRODOS (Java-based Real-time On-line Decision Support) platform. A simple source term model was used to check the applicability of the code. Finally, the code was successfully implemented to reproduce the JRODOS-formatted XML file for a detailed Fukushima Dai-ichi nuclear power plant accidental scenario. This code simplifies a vital analysis step, which would otherwise be very cumbersome, especially for a complex source term scenario involving many radionuclides, release intervals, and release heights of a nuclear accident. National Research and Innovation Agency 2025-03-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1432 10.55981/aij.2025.1432 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 57-62 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1432/1157 https://atomindonesia.brin.go.id/index.php/aij/article/view/1432/1160 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1194 2022-12-22T17:40:30Z aij:ART

Determination and Distribution Map for Radionuclides in Soil Samples from Different Location by Gamma Spectrometry Using Software Analysis Mansour, H. Najam, L. A. Abd El-Azeem, S. A. Natural Radionuclides; Cs-137; one-way ANOVA test; Gamma Spectroscopy The fundamental goal of the current study is to determine the mean activity concentrations of natural and artificial radionuclides of 226Ra, 232Th, 40K, and 137Cs using gamma spectrometry for three locations, in Egypt, Saudi Arabia, and Iraq, which are significant and vital countries in the Middle East. The mean absorbed dose rate equals 22.35, 28.96, and 43.34 nGy h-1 for Egypt, Saudi Arabia, and Iraq. The results are consistent with international reports. The dose contribution percentages for investigated locations are 24 %, 30 %, and 46 % for Egypt, Saudi Arabia, and Iraq, respectively. The obtained results were clarified by statistical measurements using one-way ANOVA test to determine the distribution and differences between the averages of the three groups under study, as they may be influenced by geological variations and human intervention. It was found that the Iraq samples followed a symmetrical, standard normal distribution, while samples from Egypt and Saudi Arabia did not. Statistically significant differences were found between the data from the three countries. National Research and Innovation Agency 2022-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1194 10.17146/aij.2022.1194 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 179-184 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1194/1038 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2183 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2184 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2181 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2175 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2173 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2174 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1194/2176 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1876 2026-02-26T03:01:50Z aij:ACKv51no3

Acknowledgement Atom Indonesia Vol 51 No 3 indonesia, atom National Research and Innovation Agency 2025-08-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1876 10.55981/aij.2025.1876 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1876/1200 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1323 2023-06-03T02:47:20Z aij:CVRv49no1

oai:ojs.aij.batan.go.id:article/1253 2023-08-29T02:15:31Z aij:ART

Geologic Influence on Radon Concentrations Levels in Cave: A Case Study of Mimpi Cave in the Maros Karst of South Sulawesi, Indonesia Syarbaini, S Kusdiana, K Wahyudi, W Iskandar, D. Widodo, S. Dewang, S. Radons; Recreational cave; Effective dose; Bantimurung; National park; South Sulawesi Radon gas in the natural environment mainly comes from the release of local bedrock geology and easily accumulate in closed spaces such as basements and caves. This study was performed to investigate the radon concentrations in Mimpi Cave, Bantimurung-Bulusaraung National Park, in the Maros karst area, South Sulawesi, and discussed a possible relationship between the radon concentrations and the local geology. Measurements were carried out using a passive detection technique with CR-39 nuclear tracks detectors by exposing it for a period of three months. The 222Rn levels measured inside the cave ranges from 64.03 Bq m‑3 to 3396.02 Bq m‑3, with an average value of 1075.05 Bq m‑3.The results are comparable with radon concentration in different caves environments reported from other surveys in several countries. Geological background of the Maros Karst areas could sustain the measured radon values, due to the presence of limestone rock with a mineral composition which can lead to higher radon concentrations in Mimpi Cave. National Research and Innovation Agency 2023-08-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1253 10.55981/aij.2023.1253 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 125-130 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1253/1085 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1253/2145 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1253/2326 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1253/2327 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1253/2328 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1253/2329 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1087 2021-06-28T15:53:36Z aij:ART

Measurements of Natural Radionuclides and 137Cs in Airborne Particulate Samples Collected from Bali and Lombok Islands (Indonesia) Syarbaini, S Wahyudi, W Suhariyono, G. Gunawan, D. Suharguniyawan, E. Natural radionuclides; Anthropogenic radionuclides; Total suspended particles; Surface air; Bali and Lombok islands Bali and Lombok islands are popular resorts and tourist destinations in the world because of their culture and beautiful natural view. The natural and anthropogenic radionuclides content in surface air of Bali and Lombok islands such as 226Ra, 232Th, 40K and 137Cs were measured at 3 monitoring stations in a period from January to December 2016. Aerosol samples were collected using a high volume total suspended particles (TSP) sampler. The activity concentrations of those radionuclides in airborne particulate matter were measured using gamma-ray spectrometry. The results show that the activity concentrations of natural radionuclides 226Ra, 232Th, and 40K ranged from 1.0 to 3.04 µBq/m3, not detected to 1.78 µBq/m3, and 0.03 to 0.49 mBq/m3, respectively. All airborne particulate matter filter samples were found to be lower than the minimum detectable activity for 137Cs, which  means that none of 137Cs is originated from atmospheric nuclear weapon test and other sources in surface air of Bali and Lombok islands. Variations of monthly activity concentrations of natural radionuclides were influenced by rainfall during study period. Furthermore, the peak concentrations of radionuclides also occur due to volcanic ash coming from Mount Rinjani eruption. National Research and Innovation Agency National Nuclear Energy Agency, Indonesia 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1087 10.17146/aij.2021.1087 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 11-16 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1087/887 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1956 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1957 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1958 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1959 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1979 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1087/1980 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1177 2021-08-30T07:42:43Z aij:ACKv47no2

Acknowledgement Atom Indonesia Vol 47 No 2 ack472, ack472 National Research and Innovation Agency 2021-06-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1177 10.17146/aij.2021.1177 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 151 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1177/975 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1316 2025-04-14T03:30:31Z aij:ART

Thermal Properties of Alpha Decay in Magnetic Field Medium Nwabuzor, P. O. Ngiangia, A. T. George, F. J. Alpha decay; Magnetic field; Phase integral; Thermodynamic properties An analytical study of alpha decay in the presence of an imposed magnetic field and some of its thermodynamic properties was considered. The study used the JWKB method to determine the allowed energy eigenvalues and mean lifetime of the decay process with the understanding that the two expressions will enable us to determine the impact of the imposed magnetic field and the select thermodynamic properties. The study reveals that the solution admits a discrete energy spectrum and the radial wave function decreases exponentially as the imposed magnetic field decreases and is square integrable with zero point energy and the presence of the imposed magnetic field, enhanced the decay rate of the particles as well as partially removed the degeneracy of the process. The four thermodynamic properties considered as shown in the graphs plotted also laid credence by enhancing the entropy and the Helmholtz free energy, while the internal energy and the specific heat at constant volume of the decay process, depreciated as the magnetic field increases as well as attainment of saturation point. Generally, the shape of the wave function plot confirmed the radioactive decay curve. National Research and Innovation Agency This research was not funded by any organization. It was purely carried out by the authors without support from any quarter. a 2024-12-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1316 10.55981/aij.2025.1316 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 1-9 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1316/1145 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2580 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2581 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2582 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2583 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2588 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1316/2589 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1156 2022-08-22T00:27:11Z aij:ART

Structure and Decay Properties of Th Isotopes Using E-RMFT Formalism Das, M. Naik, K. C. Biswal, N. Panda, R. N. Binding energy; Neutron-skin; Excitation energy; Specific heat; Decay energy; Decay half-life In the present scenario, the search for the thermally fissile nuclei is crucial and also important not only for the research background of nuclear physics but also for the great social and economic impact on the country. Many theoretical works have been performed to analyze a series of Th and U-isotopes and found that some of these isotopes are stable against α-decays and spontaneous fission. Here, we have chosen the isotopic chain of Th-nuclei for the present analysis using relativistic mean-field formalism. The work also explores a few stable isotopes in this region of the nuclear landscape, which is crucial for understanding the exotic region of the nuclear landscape. The objective of this work is to study the bulk properties such as binding energies, root mean square charge radii, neutron-proton radii, neutron skin-thickness as well as intrinsic properties such as excitation energy and specific heat for the 216-238Th-isotopic chain. Furthermore, the stability of these isotopes is investigated through their possible decay chain analysis. The relativistic mean-field theory was used to obtain the nuclear bulk properties, namely, binding energies, root-mean-square charge radii, neutron skin-thickness, and excitation energy. The steady solution of the temperature-dependent effective relativistic mean-field equations was obtained self-consistently by taking different inputs of the initial deformations. All the calculations were done for NL3, FSUGarnet and IOPB-I parameter sets for 216-238Th-isotopes. The decay energy of α (Qα) and β-decay (Qβ) were calculated from the binding energies and were further used to obtain the corresponding half-lives. We have analyzed the structural and decay properties of 216-238Th isotopes. The excitation energy and specific heat are also estimated for these considered nuclei by using the temperature-dependent effective relativistic mean-field (E-RMFT) formalism for NL3, FSUGarnet and IOPB-I parameters sets. The calculated results are compared with the available experimental data and found similar observations for all the parameter sets at a given temperature. The excitation energy study signifies the shell melting point where maybe the shape transition occurs. Three phenomenological formulae such as Viola-Seaborg, Royer and modified universal decay law are adopted for the calculation of α-decay half-lives. We found lower values of α-decay half-lives indicating a higher rate of β-decay for the isotopic chain. National Research and Innovation Agency 2022-08-11 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1156 10.17146/aij.2022.1156 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 115-123 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1156/1023 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1156/2158 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1156/2159 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1156/2160 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1156/2161 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1643 2026-02-26T03:01:50Z aij:ART

PHITS-Based Simulation of Dose Distributions and Secondary Particle Fluence from Light and Heavy Ions at Therapeutic Energies in a Water Phantom Dalumpines, C. G. M. Peñonal, G. F. I. Aringa, H. P. Convicto, V. C. Cancer, Heavy Ions, Fluence, PDD, PHITS Comprehensive dosimetric evaluation of light and heavy ions such as protons, alpha particles, carbon, and oxygen ions is essential for advancements in radiation therapy and space applications. This study employed the Particle and Heavy Ion Transport code System (PHITS) to simulate dose distributions and secondary particle fluence in a water phantom across a range of therapeutic ion energies. A 30 × 30 × 30 cm³ water phantom with 2.0 × 108 primary particles at a Source to Surface Distance (SSD) of 100 cm were irradiated using mono energetic axial source. This simulation study also evaluated particle fluence of secondary particles such as electrons, positrons, and neutrons. Results showed that positron fluence concentrates around the water phantom, dispersing more at higher energy, while neutron flux focuses along the source path. The PHITS generated Percent Depth Dose (PDD) curves illustrate varied dose deposition patterns for each ion at different energies. For the highest energy considered, the simulated Bragg peak positions deviated by not more than 4.55 % from the experimental data, with simulation uncertainties kept below 0.1 %, ensuring accurate dose analysis. Helium ions (alpha particles) exhibited favorable treatment characteristics such as lower entrance dose, minimal lateral scattering, and reduced fragmentation consistent with the experimental findings. Additionally, the spatial distributions of electrons, positrons, and neutrons show elevated concentrations near the water phantom, indicating potential benefits for enhancing treatment precision. National Research and Innovation Agency Dr. Hiroshi Takemiya, Japan Atomic Energy Agency (JAEA) DOST-Learning Resource Center 2025-10-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1643 10.55981/aij.2025.1643 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 215-220 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1643/1187 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2807 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2808 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2809 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2810 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2811 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2812 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2817 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2818 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2819 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2820 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2821 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1643/2822 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1336 2023-06-03T02:56:16Z aij:CVRv49no1

Cover Atom Indonesia Vol 49 No 1 cvr49no1, cvr49no1 National Research and Innovation Agency 2023-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1336 10.55981/aij.2023.1336 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1336/1076 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/927 2020-12-22T03:40:40Z aij:ART

Effects of Gamma Irradiation on Mating Competitiveness of Male Culex quinquefasciatus (Diptera:Culicidae) in Laboratory Ramadhani, T. Hadi, U.K. Soviana, S. Irawati, Z. Rahayu, A. Sunaryo, S Culex quinquefascuatus; Mating competitivenes; Sterile insect technique; Irradiation; Fertility rate; Culex quinquefasciatus is the main vector of lymphatic filariasis in Pekalongan City. Sterile Insect Technique (SIT) can be employed as complementary vector control for filariasis. The key success of this technique depends on the ability of laboratory-reared sterile males to mate with the wild-type females. This research aimed to was to determine the mating competitiveness, fecundity and fertility of sterile males of Cx. quinquefasciatus. The pupae of Cx. quinquefasciatus were gamma irradiated at doses of 60, 70, and 80 Gy, whereas unirradiated pupae were prepared as control. The mosquitoes emerging from the irradiated pupae were found to be able to mate with normal females in the cages. Observation was done for the mean female laying eggs, the fecundity, the fertility and the mating competitiveness. The observation data were analyzed by one-way ANOVA. The results show that the irradiated Cx. quinquefasciatus at the test doses does not affect the fecundity and the mating competitiveness, but the fertility is disturbed (sterile). A dose of 70 Gy was found to be the optimum dose, which gave a fertility rate of 1.8 % (98.2 % sterile) with a value of competitiveness (C index) of 0.568. Based on these results, irradiated Cx. quinquefasciatus can be recommended for semifield application. National Research and Innovation Agency 2020-12-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/927 10.17146/aij.2020.927 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 155-161 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/927/869 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1322 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1422 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1446 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1568 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1569 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1752 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1767 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1768 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1769 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1890 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1891 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1892 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/927/1893 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1380 2024-04-16T02:51:57Z aij:ART

Fluka Monte Carlo for Validating Low-Energy Neutron Capture Therapy Tissue with Boron and Gadolinium Bakolia, T. E. Didi, A. Sebihi, R. Adambounou, K. Hazou, E. dose, decay, boron, gadolinium, thermal Research Gap: Neutron Capture Therapy (NCT) represents a cutting-edge neutron-therapy technique for tumor treatment, but there is a gap in understanding the optimization of neutron dose deposition in tumor cells, particularly in tissues enriched with boron and gadolinium. Research Objective: This study aims to evaluate the dose deposited by thermal neutrons in adipose tissues enriched with boron and gadolinium, utilizing the Monte Carlo Fluka code. Research Methodology: The research employs Fluka, an open source Monte Carlo simulations to assess thermal neutron dose deposition in tissues. The focus is on boron and gadolinium-enriched tissues to understand their impact on neutron dose optimization. Results: Findings affirm the advantages of boron and gadolinium in enhancing neutron dose deposition within tissues. Fluka simulations demonstrate the strategic utilization of neutron properties, showcasing the potential for improved tumor management. The study highlights gadolinium's attractiveness, suggesting its promising application in clinical settings. National Research and Innovation Agency 2024-03-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1380 10.55981/aij.2024.1380 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 37-42 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1380/1109 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2387 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2419 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2420 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2421 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2422 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1380/2423 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1019 2021-08-30T07:42:43Z aij:ART

Priming Low-Dose Gamma Irradiation Increases Cellular Radioadaptation Response through the Induction of Hsp70 and SOD2 Supriyadi, S. Priming dose; Gamma ray radiation; Radioadaptation response; Hsp70; SOD2 Exposure to low-dose radiation has been demonstrated to stimulate increased cell protection when receiving subsequent challenge dose in what is known as radioadaptation response. Hsp70 and SOD, especially SOD2, are cytoprotectors against superoxide radicals generated by radiation exposure. This study aims to measure the expressions of Hsp70 and SOD2 in parotid salivary gland acinar cells as an indicator of radioadaptation response stimulated by low-dose gamma irradiation. The study used 24 male Rattus norvegicus that are divided into four groups: normal control, positive control, with 50-mGy priming irradiation, and with 100-mGy priming irradiation. The animals were immobilized without anesthetics with special tools designed especially for this study. Irradiation was carried out using a cobalt-60 (gamma ray) teletherapy unit (Philips XK-100) directed to the dorsa of the animals’ heads. High-dose gamma irradiation (2 Gy) was administered 5 hours after priming irradiation. The expression of Hsp70 and SOD2 was measured through immunohistochemical technique on the parotid salivary gland acinar cells and observed using a light microscope with 1000× magnification. Data obtained was analyzed with one-way ANOVA test (α = 0.05). The results showed that Hsp70 and SOD2 expressions in the priming irradiation groups were higher than those in control groups. The conclusion of this study: priming irradiation with low-dose gamma radiation before challenge irradiation with high-dose gamma radiation increases the radioadaptation response of salivary gland acinar cells through induction of Hsp70 and SOD2. National Research and Innovation Agency Direktorat Riset dan Pengabdian kepada Masyarakat (DRPM), Direktorat Riset dan Pengembangan, Kementrian Riset dan Pendidikan Tinggi (Ministry of Research and High Education), Indonesian. 2021-07-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1019 10.17146/aij.2021.1019 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 99-104 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1019/979 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1019/1744 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1019/1905 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1019/1906 Copyright (c) 2019 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1451 2024-12-03T02:00:48Z aij:ART

Characterizing Photon Beam Properties of a TrueBeam STx Linear Accelerator: An Evaluation of Geant4/GATE Monte Carlo Simulation Tool Performance Lam, P. H. Dung, P. T. Trung, P. Q. Photon beam; FF and FFF; Monte carlo simulation; Geant4/GATE Purpose: This study aims to investigate the characteristics of photon beams from TrueBeam STx, comparing flattening filter (FF) and flattening filter free (FFF) configurations between measurements and Monte Carlo simulation. Instruments and methods: The Geant4/GATE simulation toolkit was utilized to simulate percentage depth dose (PDD), off-axis distance profiles (profiles), dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry. Subsequently, these simulated results were compared with experimental measurements and evaluated using the gamma index method. Results: There was a good agreement between simulation and experimental measurement results in modeling the PDD and profile of photon beams. All gamma passing rate indices exceeded 97 %, 94 %, and 90 % with criteria of 3 % and 3 mm, 2 % and 2 mm, and 1 % and 1 mm, respectively. The calculated results of beam characteristics (dmax, TPR20/10, surface dose, field size, penumbra, flatness, and symmetry) were highly compatible with experimental measurements, with discrepancies less than 3 %, except for the surface dose of the 6MV FF photon beam, which had an error of 3.83 %. Conclusion: The Geant4/GATE simulation toolkit provided accurate results for simulating and investigating photon beam characteristics, aligning closely with experimental measurements. National Research and Innovation Agency Department of Radiation Oncology and Radiosurgery, 108 Military Central Hospital, Hanoi, Viet Nam Graduate University of Science and Technology, Hanoi, Viet Nam 2024-09-25 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1451 10.55981/aij.2024.1451 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 221-230 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1451/1135 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1451/2523 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1451/2524 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1451/2525 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1451/2526 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1451/2528 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1184 2022-04-12T03:55:44Z aij:ART

A Study on Radiation Hazard of Granite and Marble Widely Used in Jordan Using Gamma Ray Spectrometer Akour, A. N. Shakhatreh, S. Granite; Marble; Radioactivity; Radiation hazard Granite and marble are widely used in building construction, so possible radioactive nuclides inside them may contribute to the exposure dose to human health. The purpose of this study was to investigate the natural radioactivity concentration and assess the radiological risk limits and health care. The samples of marble and granite were pulverized into small, fine, smooth pieces and counted with the GAMMA-X (GMX) spectrometer to measure the radioactivity concentrations of 238U, 232Th, and 40K. The radiological dose, internal and external hazards, and radium equivalent activity were calculated with a standard formula. The results showed that the radioactive concentrations of 238U, 232Th, and 40K in granite were higher than those in marble. The external hazard for granite samples was below unity, while its internal hazard exceeded unity. The radium equivalent activity did not exceed the critical legal level of 370 Bq/kg as a safe level. For marble, the external and internal hazards and radium equivalent activities showed good agreement with the safe construction level. Its external and internal hazards were less than unity, whereas the radium equivalent activities were less than the critical legal level. National Research and Innovation Agency 2022-04-11 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1184 10.17146/aij.2022.1184 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 67-71 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1184/1013 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1184/2050 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1553 2025-08-07T00:44:56Z aij:ART

Exploring the Effect of Different Scanning Protocols on the Modulation Transfer Function Arjah, H. Osman, N. D. ALMasri, H. Anam, C. Aziz, M. E. Computed tomography, MTF, Iterative reconstruction The Iterative Reconstruction (IR) algorithm can enhance image quality and reduce patient dose. This study aims to evaluate the in-plane resolution (X- and Y-), in association with different IR and filtered back projection (FBP), on three different Computed Tomography (CT) scanners: General Electric (GE), Philips, and Siemens. Uniform water phantoms were scanned using 35 milligrays (mGy) and 65 (mGy and then reconstructed using 2- and 5-millimetre (mm) slice thicknesses. Images were reconstructed using the iterative Beam Hardening Correction (iBHC), Sinogram-Affirmed Iterative Reconstruction (SAFIRE), 4th generation hybrid statistical iterative reconstruction proposed by philips (iDose4), Filtered Back Projection (FBP), Adaptive Statistical iterative Reconstruction (ASiR-V), Weighted Filtered Back Projection (WFBP), Best Contrast or Brain Contrast algorithm (BC). All images were analysed using IndoQCT software. Automated Modulation Transfer Function (MTF) measurement was used to describe in-plane resolution. From the Siemens CT scanner findings, MTF at 10 % (MTF10) was increased by applying the iBHC algorithm from 0.52 to 0.57, but MTF10 of SAFIRE and WFBP showed no difference. For the Philips CT scanner, the iDose4 technique did not affect MTF10 compared to FBP, while the post-processing by BC decreases MTF10 from 0.5 to 0.49. For the GE CT scanner, the MTF is affected by radiation dose, while the ASiR-V MTF curve had no difference compared to FBP, with the highest MTF10 value of 0.67 for 35 mGy protocol compared to 0.64 for 65 mGy protocol. The image resolution is affected by CT dose and the use of reconstruction algorithms. These associated parameters may enhance or reduce image resolution. National Research and Innovation Agency 2025-07-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1553 10.55981/aij.2025.1553 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 165-171 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1553/1177 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2731 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2749 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2750 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2751 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2752 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1553/2753 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1266 2023-06-03T02:55:28Z aij:ART

Simulation of Leksell Gamma Knife-4C System with Different Phantoms Using PHITS and Geant4 Hung, B. T. Duong, T. T. Ha, B. N. Leksell gamma knife; Reference computational phantoms; PHITS; Geant4 This study used PHITS and Geant4 code packages to simulate a Leksell Gamma Knife system in order to determine radiation dose distribution in two types of phantoms. The results observed in the water phantom with configurations of single source and 201 sources are in good accord with the prior research, including both simulation and experiment. Several characteristics of Leksell Gamma Knife 4C, such as dose profiles, output factor, FWHM, and penumbra size, are calculated based on Monte Carlo simulations, which show the best consistency with other results. The output factors for collimators of 14 mm, 8 mm, and 4 mm are 0.984, 0.949, and 0.872, respectively. The simulation results with an adult mesh-type reference phantom reveal considerable similarities with the established radiosurgery plans. It indicates that the absorbed dose in brain tumors was highest when utilizing the 18 mm collimator and subsequently reduced with collimator size to 0.65, 0.25, and 0.5 with the 14 mm, 8 mm, and 4 mm collimators, respectively. The absorbed dose has a very low value for other essential organs and decreases with distance from the brain tumor. These findings may explain why the dose to organs decreases linearly as target distance, volume, and collimator size increase. National Research and Innovation Agency the Vietnamese Ministry of Education and Training, grant number B2020-BKA-20. 2023-03-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1266 10.55981/aij.2023.1266 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 13-20 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1266/1061 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1266/2231 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1266/2232 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1266/2233 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1266/2234 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1633 2026-06-05T09:24:06Z aij:ART

Comparison of Electron Density and Absorption Dose Values of Artificial Boluses as Tissue Substitutes Putri, D. R. Hentihu, F. K. Stevenly, R. J. Putri, E. R. Absorbed Dose; Bolus; Electrons; Photons; Relative Electron Density (RED) According to the Skin Cancer Foundation (SCF), approximately 1.8 million new cases of Squamous Cell Carcinoma (SCC) were reported globally in 2023. Radiotherapy remains a common treatment modality for SCC. However, delivering the maximum dose directly to the skin surface is often impeded by the skin-sparing effect of high-energy photon and electron beams. To overcome this limitation, a bolus, a tissue-equivalent material, is applied to bring the dose closer to the surface. This study aims to evaluate the electron density values derived from CT images and the absorbed doses of boluses fabricated from three different materials: resin Lycal 1079 (a propylene glycol-based compound), silicone rubber (polydimethylsiloxane), and plasticine (a mixture of stearate salt and glycerin). Dosimetric measurements were conducted using 6 MV photon beams and 12 MeV electron beams. Image analysis was performed using ImageJ and Matlab softwares. The irradiation setup employed a Source-to-Surface Distance (SSD) of 100 cm and a 10 × 10 cm² field size. Relative Electron Density (RED) values obtained from ImageJ for the resin and silicone rubber boluses were 1.007 and 1.188, respectively, while Matlab yielded RED values of 1.094 for resin and 1.194 for silicone rubber. For the plasticine bolus, both software tools produced a consistent RED value of 1.101. The findings indicate that beam energy has a significant impact on the absorbed dose at various phantom depths. Furthermore, all bolus materials increased the absorbed dose compared to setups without a bolus. Among the three materials, the resin bolus exhibited the most favorable characteristics, with a RED value closely approximating that of breast and skin tissue, highlighting its potential as an effective and economical tissue-equivalent bolus for clinical radiotherapy applications. National Research and Innovation Agency 2026-06-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1633 10.55981/aij.2026.1633 Atom Indonesia; Article In Press 2356-5322 0126-1568 10.55981/aij.v52i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1633/1218 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2736 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2737 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2946 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2969 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2970 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2971 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2972 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2973 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1633/2974 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/869 2020-09-25T01:46:31Z aij:ART

Characterization of Fe-Chitosan-Succinate- NN’-Methylene Bis-Acrylamide as Ion Imprinted Polymer Suhartini, M. Anwar, S. Saefumillah, A. Prayitno, S. Sudirman, S Ion imprinted polymer; Chitosan succinate; NN’-Methylene Bis-Acrylamide; Tripolyphosphate; Gamma irradiation High level of phosphate in the aquatic environment can reduce the amount of dissolved oxygen in the water which is harmful to the preservation of aquatic ecosystems. However, ion-imprinted polymer (IIP) is available to adsorp tripolyphosphate (TPP). In this study, Fe (III)-chitosan-succinate-tripolyphosphate complex was synthesized with NN’-Methylene Bis-Acrylamide (MBA) as a crosslinking  agent and gamma-ray as reaction initiator. The aim of the study is to observe the physical and chemical characteristics of radiation-induced crosslinking of IIP in the present of MBA. The results show that tripolyphosphate ion adsorption capacity on the Fe-chitosan-succinate-MBA ion-imprinted polymer improved by 75.62 % than that of the non-imprinted polymer.The Differential Scanning Calorimetry (DSC) analysis shows a significant difference in the endothermic, exothermic and glass transitions of chitosan, chitosan-succinate when compared to their complex salts. The Fourier Transform Infra-Red (FTIR)  analysis shows the presence of tripolyphosphate groups bonded by Fe-Chitosan-succinate-MBA ion imprinted polymer. Scanning Electron Microscope (SEM) analysis of IIP exhibits a significantly difference surface shapes between IIP with template still within the polymer matrix and after removal. National Research and Innovation Agency National Nuclear Energy Agency 2020-08-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/869 10.17146/aij.2020.869 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 107-113 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/869/843 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1279 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1305 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1654 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1655 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1850 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1851 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/869/1852 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1313 2023-12-19T03:11:18Z aij:ART

Dose Response of Personnel OSL Dosimeter to the Cesium-137 and 80 kVp X-ray Exposure Jumpeno, E. B. Anggraeni, R. Barokah, S. N. Syaifudin, R. Personnel OSL dosimeter; Hp(10); Cs 137; X-ray Over the years, several types of dosimeters have been introduced for accurate dose assessment. The OSL dosimeter is one of them. It is used to monitor personnel dose from external exposure. In this paper, dose response of OSL dosimeters in terms of Hp(10) to Cs‑137 gamma and 80 kVp X‑ray radiation will be studied. The dosimeters were irradiated using Cs‑137 gamma and 80 kVp X‑ray to 0.5 mSv, 1 mSv, 3 mSv, 5 mSv, and 10 mSv at a distance of 200 cm, and all of them were subsequently read. Half of the dosimeters that were previously irradiated with a dose of 1 mSv and 5 mSv were read 30 times. The other half of the dosimeters were re-read on day 30 and day 60 from the initial reading. The study shows that relations between measured dose and exposure dose for Cs‑137 gamma and 80 kVp X‑ray irradiation are linear with correlation coefficients (R2) of 0.9997 and 0.9987, respectively. When the OSL dosimeters were read repeatedly, a dose reduction for each reading occured by 0.4 % and 0.5 % on Cs‑137 gamma and 80 kVp X‑ray, respectively. Dose reading on day 60 after Cs‑137 gamma irradiation showed fading of 3.6 % and 2.7 % on OSL dosimeter exposed to 1 mSv and 5 mSv, respectively, whereas fading effect on 80 kVp X‑ray irradiation showed values of 5.9 % and 8.8 % for the two doses. National Research and Innovation Agency National Research and Inovation Agency 2023-12-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1313 10.55981/aij.2023.1313 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 209-213 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1313/1099 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1313/2368 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1313/2369 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1313/2370 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1313/2371 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1313/2372 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1301 2024-09-10T08:58:51Z aij:ART

Atmospheric Nitrogen Plasma-Induced for Embedding NH2@Cubic-Bicontinuous Mesoporous Silica as Uranium (VI) Adsorbent Candidate in Seawater Pamungkas, N. S. Wongsawaeng, D. Swantomo, D. Kamonsuangkasem, K. Chio-Srichan, S. Nitrogen plasma; Cubic bi-continuous; Mesoporous silica; Amine-modified; Uranium; Adsorption This work aims to achieve interesting progress in uranium extraction by introducing a promising strategy that utilizes atmospheric nitrogen plasma-induced amine modification of CBC (Cubic Bi-continuous) material, providing a compelling pathway to enhance CBC's adsorption properties specifically for uranium harvesting. CBCs mesoporous silica samples were prepared by mixing the Pluronic F-127 as a template and TEOS (Tetraethyl Orthosilicate) as silica sources in the sol-gel process under acidic conditions. The obtained CBCs were treated using nitrogen plasma at room temperature (RT) under atmospheric pressure in a customized-borosilicate plasma reactor. Subsequently, the treated CBSs were grafted with amine groups. The final samples were characterized using SAXS (Small Angle Synchrotron X-ray Scattering) to determine the phase and structure, SEM-EDS (Scanning Electron Microscopy-Energy Dispersive Spectroscopy) analysis to quantify the presence of silica, oxygen, and embedded nitrogen, and Specific Surface Area (SSA) Analyzer using Brunauer-Emmett-Teller (BET) method to determine the specific surface area and pore size distribution. The SAXS profiles indicate that the obtained samples can be classified as CBCs Im3m mesoporous silica. The presence of silica, oxygen, and nitrogen was verified through SEM-EDS analysis, with approximate compositions of 36-37 %, 51-62 %, and 0.7-1.0 %, respectively. The use of SSA analysis further supported the findings, confirming the typical adsorption isotherm IV model. The specific surface areas were measured to be 371 m2/g for pure CBC, 573 m2/g for P1-CBC, and 607 m2/g for P2-CBC. The pore size distribution analysis revealed mesoporous characteristics within the material, with pore sizes ranging from 4 to 6.5 nm. On a batch laboratory scale, the material achieved the highest adsorption capacity of 15.68 mg-U(VI)/g-NH2@P1-CBC from natural seawater after 1 hour of contact time. National Research and Innovation Agency Chulalongkorn University Synchrotron Light Research Institute (SLRI), Thailand 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1301 10.55981/aij.2024.1301 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 165-174 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1301/1122 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2455 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2460 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2469 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2456 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2457 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2458 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1301/2459 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1145 2022-04-12T07:21:36Z aij:ART

Assessment of TMSR-500 Shutdown Capability Khakim, A. Firmanda, F. R. Pramono, Y. Suharyana, S TMSR-500; Liquid fuel; Shutdown capability; MCNP6; Control log; Fuel drain tank The molten salt reactor (MSR) is a generation IV reactor with liquid fuel having nearly zero excess reactivity. Due to the very low excess reactivity, it requires a small number of control rods worth to shut down the reactor. However, as it operates at high temperatures, the core reactivity increases as the fuel temperature cools down during shutdown. In such a case, the control rods might not be able to keep the reactor at a subcritical state, and consequently, the fuel must be removed from the core for long-term shutdown into a fuel drain tank (FDT) below the core. This paper is intended to assess the shutdown capability of the first active shutdown system and fuel drain tank of ThorCon MSR by doing neutronic calculations with MCNP6. The results indicated that the control rods having reactivity worth ‑1.699 %dk/k are unable to maintain the core at a subcritical state as the core excess reactivity increases to +7.760 %dk/k when the fuel reaches room temperature. Therefore, the fuel must be drained to FDT to be cooled down and kept subcritical. Evaluation for various cases of FDT produced the highest multiplication factor of 0.57008 ± 0.00004 at the most conservative condition. The multiplication factor is well below the critical state of 1.0. The evaluations suggest that soon after the control rods shut the reactor down, the fuel has to be drained to FDT to maintain shutdown condition and dissipate the decay heat. National Research and Innovation Agency BAPETEN 2022-03-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1145 10.17146/aij.2022.1145 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 1-7 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1145/1003 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2008 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2009 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2010 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2011 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2012 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2013 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2014 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2102 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2103 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2104 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1145/2105 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1660 2025-04-14T03:30:31Z aij:ACKv51no1

Acknowledgement Atom Indonesia Vol 51 No 1 indonesia, atom National Research and Innovation Agency 2024-12-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1660 10.55981/aij.2025.1660 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1660/1167 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1178 2022-12-22T17:40:30Z aij:ART

Detection of Radon Exhalation from Various Building Materials Using CR-39, RAD7, and Biosensors Albazoni, B. J. Almayahi, H. J. Biosensor; RAD7; CR-39; Radon detection Study aimed to design and manufacture two biosensors, namely BIOS-I and BIOS-II, for 222Rn and Pb+2 measurements in building materials and soil samples. For comparison, the conventional detectors of RAD7 and CR-39 were used. The biosensor material used was based on ssDNA rich guanine or primer. The two biosensors have a difference in the sequence of the nitrogenous bases. The measurement revealed that the average of 222Rn exhalation by the BIOS-Ι was 373.30 Bqm-3, while the BIOS-ΙΙ was 342.29 Bqm-3. The average 222Rn exhalation measured by the CR-39 detector was 326.17 Bqm-3, whereas by the RAD7 detector it was 319.95 Bqm-3. This study found that 222Rn exhalation in the Indian and Chinese granites, soil, and Iraqi mosaic samples was higher than the limits recommended by WHO, while the rest of the samples were within the permissible limits. It is also known that there is a very weak positive correlation between BIOS-Ι or BIOS-ΙΙ and humidity, while a very weak negative correlation was found between them and temperature. There is a very strong positive correlation between radon exhalation recorded by RAD7 and humidity. On the other hand, there are no statistically significant differences between BIOS-I and BIOS-II at (level 0.01), while there are statistically significant differences between BIOS-I and CR-39 or RAD7 at level 0.01. It was concluded that the manufactured biosensors have better detection for radon than RAD 7 and CR-39 detectors. National Research and Innovation Agency 2022-12-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1178 10.17146/aij.2022.1178 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 225-230 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1178/1050 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1178/2197 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1178/2198 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1178/2199 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1178/2200 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1178/2201 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1558 2026-04-06T04:06:37Z aij:ART

Comparative Assessment of Radioactive Contamination in APR 1400 Reactor During SBO and TMI Accidents Ghaderinia, F. Rahgoshay, M. Jafari, J. Severe accident; APR 1400; Radiological contamination; Station blackout, Containment failure An alternative approach to estimate the tissue phantom ratio (TPR) at depths of 20 cm and 10 cm (TPR₂₀,₁₀) under non-reference conditions is required to address situations where a 10 × 10 cm² field size is not achievable on a specific linear accelerator (LINAC) during a beam quality test. This study aims to estimate the TPR20,10 under non-reference conditions using a geometric sequence approach, and to compare it with the TPR₂₀,₁₀ under non-reference conditions estimated using the Sauer method, the Palmas method, a linear fit approach, as well as with the TPR₂₀,₁₀ under reference conditions calculated using the TRS-398 protocol. The first step in this study was measuring the percentage depth dose (PDD), D20cm, and D10cm with field size variations from 4 × 4 cm² to 10 × 10 cm² for both 6 MV and 10 MV X-ray beams. The PDD were used to estimate the TPR₂₀,₁₀ using a geometric sequence approach, the Sauer method, the Palmans method, and a linear fit approach, and to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The D20 cm and D10 cm were also used to calculate the TPR₂₀,₁₀ using the TRS-398 protocol. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach were 0.683 ± 0.004 and 0.742 ± 0.005, respectively. The level of precision that could be reached by the geometric sequence approach is potentially equivalent to the TRS-398 protocol, the Sauer method, the Palmans method, and the linear fit approach. The TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence method did not show a significant difference compared with the TPR₂₀,₁₀ calculated using the TRS-398 protocol. However, the TPR₂₀,₁₀ for 6 MV and 10 MV X-ray beams estimated using the geometric sequence approach showed a significant difference compared with those TPR₂₀,₁₀ estimated using the Sauer method and the Palmans method. National Research and Innovation Agency 2026-03-12 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1558 10.55981/aij.2026.1558 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 43-48 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1558/1207 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1558/2918 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1558/2919 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1558/2920 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1558/2921 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/45 2020-07-22T01:07:52Z aij:ART

Measurements of Residual Stresses in Cold-Rolled 304 Stainless Steel Plates Using X-Ray Diffraction with Rietveld Refinement Method Parikin, P Killen, P. Rafterry, A. 304 stainless steel, cold rolling, X-ray diffraction, Rietveld refinement method, and residual stress. The determination of the residual stresses using X-ray powder diffraction in a series of cold-rolled 304 stainless steel plates, deforming 0, 34, 84, 152, 158, 175 and 196 % reduction in thickness has been carried out. The diffraction data were analyzed using the Rietveld structure refinement method. The analysis shows that for all specimens, the martensite particles are closely in compression and the austenite matrix is in tension. Both the martensite and austenite, for a sample reducing 34% in thickness (containing of about 1% martensite phase) the average lattice strains are anisotropic and decrease approximately exponential with an increase in the corresponding percent reduction (essentially phase content). It is shown that this feature can be qualitatively understood by taking into consideration the thermal expansion mismatch between the martensite and austenite grains. Also, for all cold-rolled stainless steel specimens, the diffraction peaks are broader than the unrolled one (instrumental resolution), indicating that the strains in these specimens are inhomogeneous. From an analysis of the refined peak shape parameters, the average root-mean square strain, which describes the distribution of the inhomogeneous strain field, was predicted. The average residual stresses in cold-rolled 304 stainless steel plates showed a combination effect of hydrostatic stresses of the martensite particles and the austenite matrix.Received: 14 March 2008; Revised: 13 October 2008; Accepted: 6 November 2008 National Research and Innovation Agency National Nuclear Energy Agency of Indonesia 2011-12-12 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/45 10.17146/aij.2009.45 Atom Indonesia; Vol 35, No 1 (2009): January 2009; 19-36 2356-5322 0126-1568 10.17146/aij.2009.%x eng https://atomindonesia.brin.go.id/index.php/aij/article/view/45/791 Copyright (c) 2016 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1367 2023-08-29T08:26:45Z aij:ACKv49no2

Acknowledgement Atom Indonesia Vol 49 No 2 ack49no2, ack49no2 National Research and Innovation Agency 2023-05-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1367 10.55981/aij.2023.1367 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1367/1089 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1000 2021-06-28T15:53:36Z aij:ART

Synthesis and Characterization of Ordered and Disordered Mesoporous Alumina as High-Performance Molybdenum-99 Adsorbents Saptiama, I. Rindiyantono, F. Aries, A. Kaneti, Y. V. Iqbal, M. Molybdenum-99; Technetium-99m; Diagnostic; Mesoporous; Alumina Molybdenum-99 (99Mo) is the parent radioisotope of technetium-99m (99mTc),an essential medical radioisotope for diagnostic agents in nuclear medicine.In 99Mo/99mTc generator, a chromatography column system with 99Mo adsorbent as afiller is usually used to produce 99mTc in hospitals. However, it is still challenging to find high-performance adsorbentsfor Mo adsorption.We have synthesized both ordered and disordered mesoporous alumina and compared their performance as 99Mo adsorbents. These materials were prepared via a soft-templated method using a triblock copolymer as the template, followed by air calcination at 400°C.The amount of nitric acid (HNO3) and the drying time were adjusted systematically to synthesize the ordered mesoporous alumina. The obtained ordered and disordered mesoporous alumina were characterized by low-and wide-angle X-ray diffractions (XRD), nitrogen adsorption-desorption, thermogravimetric analysis (TGA), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The 99Mo adsorption capacities of these materials were evaluated by using the batch method. The experimental results show that the ordered mesoporous alumina hasa higher 99Mo adsorption capacity of 72.06 mg(Mo)g-1 than the disordered mesoporous alumina (50.12 mg(Mo)g-1). The results indicate the excellent potential of ordered mesoporous alumina as an adsorbent for the 99Mo/99mTc generator column. National Research and Innovation Agency the Program for Research and Innovation in Science and Technology (RIST-Pro) scholarship, the Ministry for research, Technology and Higher Education, Republic Indonesia 2021-04-16 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1000 10.17146/aij.2021.1000 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 45-53 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1000/896 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1695 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1699 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1910 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1988 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1989 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1990 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1000/1991 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1355 2024-04-05T22:39:48Z aij:ART

The Effect of Zinc Concentration on Bioaccumulation in Milkfish (Chanos chanos) Use of 65Zn as a Radioactive Tracer Wahyono, I. B. Muslim, M Suseno, H. Suryono, C. A. Bioaccumulation; Zinc; Milkfish; Concentration; Elimination; Depuration Bioaccumulation studies of zinc (Zn) in milkfish (Chanos chanos) have been carried out in the laboratory using a 65Zn radiotracer. The research was conducted to determine the effect of Zn concentration on the ability of Chanos chanos to accumulate and release these contaminants. Zn absorption follows the single-compartment model, and experiments were carried out until stable conditions were achieved. The stages of research were biota collection, acclimatization, bioaccumulation, and elimination. Acclimatization was carried out for biota adaptation in the experimental environment. Bioaccumulation was carried out for 7 days by placing the biota in an aquarium filled with seawater added with 65Zn radiotracer contaminants. The elimination process involves the release of contaminants from the biota by placing them in contaminant-free seawater for 7 days. The results of the bioaccumulation experiment showed that the concentration factor (CF) ranged from 0.67 - 18.18 mLgr-1 at a concentration of ZnCl2 of 1.5 ppm, and the absorption constant (ku) 1.878 - 3.267d-1 and R2 was 0.0276. The release of contaminants in depuration experiments was highest at ZnCl2 2 ppm concentrations. The percentage of retention during depuration was between 14.61 - 79.91 %, the elimination constant (ke) was 8.681, and R2 was 0.7213. National Research and Innovation Agency Faculty of Fisheries and Marine Science, Diponegoro University and Research Center for Radioisotope Technology, Radiopharmaceuticals and Biodosimetry and Research Center for Environmental and Clean Technology - National Research and Innovation Agency. 2024-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1355 10.55981/aij.2024.1355 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 71-80 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1355/1113 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2407 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2408 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2409 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2410 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2411 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1355/2413 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1122 2021-12-10T07:13:03Z aij:ART

Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2 Dwijayanto, R. A. P. Oktavian, M. R. Putra, M. Y. A. Harto, A. W. PCMSR; Thorium; Conversion ratio; Model comparison; MCNP6; Serpent-2 Passive Compact Molten Salt Reactor (PCMSR) is a thermal breeder molten salt reactor (MSR) developed in Universitas Gadjah Mada, Indonesia, run in thorium fuel cycle. Its design was initially developed using deterministic code SRAC2006 but has never been compared with other codes. This paper attempts to compare PCMSR neutronic design using Monte Carlo codes MCNP6 and Serpent-2 with ENDF B/VII.0 continuous neutron cross-section library. The reactor was run in a pure thorium fuel cycle with lithium fluoride as its carrier salt. The analyzed parameters were effective multiplication factor (keff), temperature coefficient of reactivity (TCR), void coefficient of reactivity (VCR), and conversion ratio (CR). The result shows that there are several important discrepancies between the original calculation and this research. The Monte Carlo calculations implied that PCMSR core was able to be critical using lower fissile concentration than previously designed, but failed to reach CR above unity. While the TCR value was found to be negative, the VCR value was positive up until the 10 % void fraction. The PCMSR core suffered from ineffective neutron moderation and high neutron leakage. These findings imply that the previous PCMSR neutronic design is inaccurate. For PCMSR to be able to operate as a thermal breeder MSR, geometrical modifications must be performed to improve neutron moderation and reduce neutron leakage. National Research and Innovation Agency Centre for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency 2021-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1122 10.17146/aij.2021.1122 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 191-197 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1122/993 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/1923 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/1924 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/1925 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/1927 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/2038 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1122/2065 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1526 2025-04-14T03:30:31Z aij:ART

Radiation Dose and Image Quality of Bladder Cancer Patients Analysis on Abdominal CT-Scan Examinations Anthon, R. Intifadhah, S. H. Putri, E. R. Abdomen; Contrast to Noise Ratio (CNR); Dose; Image; Signal to Noise Ratio (SNR) The bladder is a subperitoneal, hollow muscular organ that acts as areservoir for urine and located in the lower abdomen. Bladder cancer is one of health issues that can affect many people each year. Bladder cancer ranks as the 10th most common cancer worldwide. Early management includes cancer screening using abdominal CT-Scan. The objective of this study was to analyze the radiation dose received by patients and the image quality of patients underwent abdominal CT scans based on the Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values obtained. Data analysis management, specifically using quantitative analysis techniques, involved observing 20 bladder cancer patients with a total of 2,653 images. The IndoseCT software was used for analyzing the radiation dose to patients, while the IndoQCT software was used for analyzing image quality in CT-Abdomen examinations based on Signal to Noise Ratio (SNR) and Contrast to Noise Ratio (CNR) values. The results showed that the radiation dose received by patients during CT-Abdomen examinations was higher than the dose output by the device. The maximum dose output by the device (CTDIvol) was 50.10 mGy, and the minimum was 6.70 mGy, while the maximum dose received by patients (SSDE) was 53.34 mGy, and the minimum was 9.34 mGy. The image quality results for CT-Abdomen examinations based on SNR and CNR values indicated that the image quality obtained was adequate for diagnostic purposes. National Research and Innovation Agency 2025-02-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1526 10.55981/aij.2025.1526 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 27-33 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1526/1153 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1526/2634 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1269 2022-08-24T22:02:17Z aij:CVRv48no2

Cover Atom Indonesia Vol 48 No 2 cover48no2, cover48no2 National Research and Innovation Agency 2022-07-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1269 10.17146/aij.2022.1269 Atom Indonesia; Vol 48, No 2 (2022): August 2022 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1269/1030 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1467 2026-02-26T03:01:50Z aij:ART

The Effect of Loop Inclination on Natural Circulation Mass Flow Rate and Heat Removal Inside Rectangular Passive Cooling Loop Budiyanto, N. R. Deendarlianto, D Yuliaji, D. Oktaviandi, R. Raharjo, E. P. A. Mariyadi, S. A. Pamungkas, A. E. Setiawan, P. H. Budiman, A. A. Juarsa, M. Inclination angel; Natural circulation; Passive cooling; Heat removal; Mass flow rate; FASSIP-04 Ver.0 The use of passive cooling systems as a reactor safety measure has become a key approach to preventing future incidents similar to the Fukushima Daiichi NPP accident. These systems operate based on natural circulation, a process driven by temperature differences and elevation between the heat source and heat sink. Key design factors, such as the inclination angle of the rectangular loop, significantly influence this circulation. This study aims to investigate the effects of different inclination angles of the rectangular loop and variations in the initial water temperature in the Water Heating Tank (WHT) on the flow rate and heat removal capability. The research was conducted experimentally using a natural circulation rectangular loop facility, FASSIP-04 Ver.0, which has an inner diameter of 26.64 mm, a rectangular loop height of 2280 mm, and a width of 780 mm. The experimental variations were achieved by adjusting the water temperature inside the WHT to 50°C, 70°C, and 90°C. Meanwhile, the inclination angle of the loop was set to 30°, 60°, and 90° mass flow rate and heat removal capability was influenced by both the loop inclination angle and the water temperature in the WHT. The highest values were observed at a 90° inclination angle and a set temperature of 90°C, with a mass flow rate of 0.0241 kg/s, and heat removal rates of qH = 0.791 kW, qC = 0.489 kW. The resulting buoyancy force was stronger under these conditions, leading to greater heat removal through natural circulation compared to free convection, thereby increasing both mass flow rate and heat removal efficiency. National Research and Innovation Agency RIIM batch-1 LPDP Mandatori BRIN 2025-12-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1467 10.55981/aij.2025.1467 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 259-271 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1467/1191 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2447 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2791 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2853 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2850 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2849 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2851 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2852 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1467/2863 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1277 2023-08-29T02:15:31Z aij:ART

Homogeneity Test on Collimators for Boron-Neutron Capture Therapy based on SNI 8506:2018 Santosa, S. Khotimah, K. Yasmine, H. Boron-neutron capture therapy; Homogeneity test; Neutron collimator A serial homogeneity test based on Indonesian Standard SNI 8506:2018 were undertaken to investigate 12 manufactured collimators by using double wall single image radiography (DWSI) technique with an x-ray machine ranging from 120 to 150 kV. The standard stated that the film density should be measured on seven different points, and the result obtained must not exceed ± 0.05 from the average density. This paper outlines a testing work for the collimators, calculating the density on six different points in the film. Six different points were selected due to technical constrains of the collimator manufacturing and radiography capabilities of the selected laboratory. The results of film the density for the 12 collimators are: (1) 2.59; (2) 2.57; (3) 2.14; (4) 1.88; (5) 2.10; (6) 1.96; (7) 2.33; (8) 2.28; (9) 2.06; (10) 2.18; (11) 2.24; and (12) 2.33. The result shows that collimator-2 has the most homogenous density. This study concludes that established parameters and process are needed to manufacture the collimator for BNCT in achieving proper performance testing based on the standard. National Research and Innovation Agency Khusnul Khotimah (BRIN) , Hanna Yasmine (BRIN) 2023-08-06 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1277 10.55981/aij.2023.1277 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 97-101 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1277/1083 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2166 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2299 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2300 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2310 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2311 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2312 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2313 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2315 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1277/2314 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1108 2020-12-23T05:15:12Z aij:PRVv46no3

Preface Atom Indonesia Vol 46 No 3 prfc46no3, prfc46no3 National Research and Innovation Agency 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1108 10.17146/aij.2020.1108 Atom Indonesia; Vol 46, No 3 (2020): December 2020 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1108/871 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1112 2021-08-30T07:42:43Z aij:ART

Comparisons of Water-Equivalent Diameter Measured on Images of Abdominal Routine Computed Tomography with and without A Contrast Agent Nitasari, A. Anam, C. Budi, W. S. Wati, A. L. Syarifudin, S Dougherty, G. Abdominal routine; Size-specific dose estimate (SSDE); Water-equivalent diameter (DW) The size-specific dose estimate (SSDE) is a metric for an estimation of patient dose in computed tomography (CT). The SSDE strongly depends on the       water-equivalent diameter (DW). In abdominal CT examinations, a contrast agent is sometimes used to more clearly visualize tissue lesions. The Hounsfield unit (HU) of CT images with and without the use of a contrast agent at specific areas is slightly different and it may affect the DW value. This study aimed to compare the DW values calculated from axial CT images in patients who had undergone routine abdominal scans both with and without the use of a contrast agent. Axial images of 144 patients with a weight range of 3.5 kg to 90 kg who had undergone routine abdominal scans both with and without the use of a contrast agent using a Siemens Sensation 64 CT scanner were retrospectively collected. The DW values were automatically calculated using the Matlab-based IndoseCT (version 15a) software. The results show the percentage difference between DW,contrast and DW,non-contrast is below 2 %.As a result, the mean SSDEcontrast is 1.5 % smaller than SSDEnon-contrast. Due to the effect of a contrast agent on the DW and SSDE values is below 2 %, the axial images of CT abdomen without the use of a contrast agent can be used as the accurate estimation of DW and SSDE for images with the use of a contrast agent. National Research and Innovation Agency World Class Research University (WCRU), Diponegoro University, 2021 2021-08-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1112 10.17146/aij.2021.1112 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 135-139 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1112/984 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1919 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1931 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1932 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1933 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1934 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1935 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1936 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1937 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1938 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1939 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1944 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1945 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1946 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1112/1947 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1425 2024-12-03T02:00:49Z aij:ART

Dose Response of Hp(0.07) on TLD-700 and TLD-900 Based Ring Dosimeters to the Sr-90 Exposure Jumpeno, E. B. Anggraeni, R. Putri, M. Muharani Barokah, S. N. Adisti, F. N. Hp(0.07); TLD-700; TLD-900; Ring dosimeter; Sr-90 The preparation of radiopharmaceuticals may necessitate close contact with the radioactive source. In this case, high-energy beta-emitting nuclides can cause a high exposure. There are two methods of measuring the dose in the extremities, including using a bracelet and a ring dosimeter. In this study, the response of Hp(0.07) dose in TLD-700 and TLD-900-based ring dosimeters to Sr-90 beta radiation will be compared for parameters of distance, time, and angle of irradiation. The dosimeters were irradiated using Sr-90 at a distance of 5, 7, and 10 cm from the source surface and all of them were subsequently read with TLD Reader. The same type of dosimeters were exposed to Sr-90 for 1 day, 2 days, and 3 days at a distance of 7 cm and read. At a distance of 7 cm, the other dosimeters were irradiated at angles of 30°, 60°, -30°, and -60°, and then read. The study shows that the relationship between the distance of irradiation to Hp(0.07) dose is polynomial with a correlation factor of 1, both for TLD-700 and TLD-900-based ring dosimeters. The dose response at the variation of irradiation time showed linear behavior with correlation coefficients of 0.9942 and 0.9999 for TLD-700 and TLD-900, respectively. The decrease in Hp(0.07) response in TLD-700 reached 14-31 % for the irradiation angle of ±30o and 23-27 % in TLD-900 for the same angle. Meanwhile, the decrease in Hp(0.07) response at the angle of irradiation ±60o reached 48 % for TLD-700 and 66-67 % for TLD-900. National Research and Innovation Agency National Research and Inovation Agency and the General Manager Dosimetry Laboratory of NuklindoLab 2024-11-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1425 10.55981/aij.2024.1425 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 267-271 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1425/1141 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2562 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2563 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2564 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2565 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2568 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1425/2579 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1158 2022-08-22T00:27:11Z aij:ART

Patient Radiation Doses in Interventional Cardiology Procedure Hiswara, E. Kartikasari, D. Nuraeni, N. Sofyan, H. Sandy, K. Y. P. Interventional cardiology; Patient doses; Air kerma; Kerma-air product; Cancer risk Interventional cardiology is a minimally-invasive imaging procedure that allows medical doctor to evaluate and treat structural heart diseases. Due to its main advantages of avoidance of the scars and pain, as well as long post-operative recovery, interventional cardiology procedures have rapidly been growing. However, the increasingly complex and time-consuming procedures in interventional cardiology may increase the radiation exposure received by patients. This paper describes a study to measure patient radiation doses in terms of air kerma and kerma air-product (KAP) for various types of interventional cardiology procedures conducted in Indonesia. The measurements were performed at the interventional cardiology or cardiac catheterization facilities in sixteen hospitals in ten cities in Indonesia during the years of 2015 to 2019. A total of 147 procedures conducted on adult patients were used in this study. The type of procedure, total KAP, and air kerma were recorded after each procedure was completed. The demographic data of the patients were also recorded. The results showed that the mean air kerma and KAP measured for CA (coronary angiography) procedure were 680.73±57.85 mGy and 12.52±5.86 Gy cm2, respectively, while the values for PCI (percutaneous coronary intervention) procedure were 890.66±38.76 mGy and 20.18±9.37 Gy cm2, respectively. These results are well within the ranges reported by other previous studies. The results are somewhat affected by the     body mass index of patients, while the fatal cancer risks among patients of CA and PCI procedures are comparable with those among interventional radiology procedures patients. National Research and Innovation Agency National Nuclear Energy Agency Center for Technology of Radiation Safety and Metrology 2022-07-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1158 10.17146/aij.2022.1158 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 81-85 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1158/1020 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1158/2024 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1541 2025-08-07T00:44:56Z aij:ART

Investigation of Dose Effect of ICRP110 Male and Female Head Phantoms During BNCT and PBFT by Monte Carlo Simulations Korkut, H. Korkut, T. Singh, V. P. BNCT; PBFT; Brain; Geant4; Radiation Dose; LET; (Linear Energy Transfer) Boron Neutron Capture Therapy (BNCT) and Proton Boron Fusion Therapy (PBFT) are of great interest in the field of radiation oncology. These treatment methods may offer different advantages and disadvantages depending on the type of tissue involved, as well as the location and size of the cancerous area. In this study, radiation dose effect of BNCT and PBFT on the brain, one of the most sensitive organs of the human body, was examined comparatively, based on the ICRP110 male and female head phantom models by using GEANT4 Monte Carlo simulations. Additionally, some necessary LET (Linear Energy Transfer) calculations are also presented in the article. Dose, LET and Energy deposition values of GEANT4 calculations were presented for BNCT and PBFT therapies in details for male and female phanthom comparatively. National Research and Innovation Agency 2025-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1541 10.55981/aij.2025.1541 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 179-184 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1541/1179 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1541/2766 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1541/2767 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1541/2768 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1541/2769 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1541/2770 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1213 2023-06-03T02:55:28Z aij:ART

Some Metal Oxide-Natural Rubber Composites for Gamma- and Low-Energy X-Ray Radiation Shielding Fisli, A. Yulianti, E. Hanurajie, B. Sukaryo, S. G. Mashadi, M Rivai, A. K. Prastanto, H. Fathurrahman, M. I. Polymers composites; Oxide metal; Shielding material; X-ray radiation; Gamma-ray radiation This work studied protective material consisting of several metal oxide composites (Pb3O4, WO3, SnO2, and Bi2O3)-natural rubber (NR) for X-ray and gamma-ray shielding. The composites were prepared through open milling and vulcanization processes and further characterized by scanning electron microscope (SEM), X-ray diffraction (XRD), rheometry analysis, and density gauge. The attenuation coefficient of the sample was investigated using X-ray generators with voltages ranging from 50 to 140 kV and gamma-ray energies ranging and 356 to 1250 keV, respectively. The experimental results show that the linear attenuation coefficient of NR filled with metal oxides was significantly improved compared to pure NR. For gamma-ray 661 keV, the HVL of NR decreased from 9.0 cm to between 4.4 - 6.2 cm after it was filled with metal oxides. The Bi2O3-NR is the best suitable material for gamma-ray attenuation, followed by Pb3O4-NR, WO3-NR, and SnO2-NR. Meanwhile, for x-rays, the HVL of NR decreased from 2.0 cm to between 0.17 -0.31 cm after it was filled with metal oxides. The proposed metal oxide-NR composites can be appropriate as a flexible protective material for manufacturing wearable radiation shielding products such as gloves, aprons, rubber underwear, and other wearable materials. National Research and Innovation Agency 2023-04-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1213 10.55981/aij.2023.1213 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 45-52 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1213/1066 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1213/2255 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1213/2256 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1213/2257 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1213/2258 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1213/2259 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/960 2020-12-29T20:55:43Z aij:ART

The Use of Image Processing and Analysis in Automated Biological Dosimetry Ramadhani, D. Syaifudin, M. Purnami, S. Naroeni, A. Biodosimetry; Dicentric chromosome; γH2AX; Image analysis; Micronuclei Biological dosimetry based on cytogenetic markers such as dicentric chromosome (DC) and micronuclei (MN) is, until now, the most frequently used method to estimate the radiation dose in the radiological accident event. Another biomarker that recently gains popularity in biodosimetry is γH2AX. All these three assays are microscope-based biodosimetry techniques, and therefore need manual scoring to estimate the radiation dose. Unfortunately, the manual scoring of these assays is time-consuming and labor-intensive. In the case of a large-scale radiological accident when many people are exposed to radiation, it is very useful to use image processing and analysis in the scoring process to obtain a faster result. Several commercial systems or open-source image processing software packages already developed automated scoring of DC, MN, and γH2AX assays. This article describes how image processing and analysis were applied in automated biodosimetry based on the DC, MN, and γH2AX assays. National Research and Innovation Agency Ministry of Research, Technology and Higher Education of the Republic Indonesia 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/960 10.17146/aij.2020.960 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 127-133 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/960/852 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1505 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1632 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1762 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1824 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1825 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1869 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1880 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1881 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1882 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1883 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1884 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1885 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1894 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1895 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1896 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/960/1897 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1305 2024-04-16T01:40:53Z aij:ART

Investigation of Tissue Components Impacts on Dose Enhancement Factor Using Monte Carlo Code AL-suhbani, M. N. Baghous, N. E. H. Serag, S. EL Mahjoub, C. Ait-Mlouk, L. Zia, A. Hamid, B. Azougagh, M. Brachytherapy, Dose Enhancement Factor, gold nanoparticle, MCNP6, GATE. Despite the progress of science in cancer treatments and radiotherapy improvements, there are still several side effects that occur during tumors treatment, particularly on healthy tissues surrounded tumors. Newer treatment methods are being explored lately, one of which is the use of nanoparticles, wherein the tumor is injected with gold nanoparticles. Its aim is to enhance tumor sensitivity to radiation and reduce radiation damage to healthy tissues. Tissue type may play an effective role in enhancing the dose being received under the use of nanoparticles. This study aims to find the effect of different tissue components on dose enhancement factor through MCNP6 and GATE simulations, as well as to accurately compare  the simulation results of these two code packages for dose enhancement factors. A 125I brachytherapy source was simulated in phantoms for five tissues or materials (adipose tissue, breast tissue, soft tissue, water, and brain tissue). MCNP6 simulation code was validated by comparing its results with a previous study by Cho et al. Gold nanoparticles were injected as a mixture at a concentration of 7 mg/g into tissues inside a tumor. MCNP6 and GATE simulation results were compared. It was estimated from MCNP simulations that the highest radiation dose enhancement of 2.34 occurs in adipose tissue while lowest dose enhancement of 1.69 is in brain. In comparison, from GATE results, the estimates were that the highest value of dose enhancement factor also occurred in adipose tissue at 2.01, and the lowest value in brain at 1.48. The comparison between two codes suggest that they are compatible with the percentage difference in all tissues being less than 15 %. This study confirms that both MCNP6 and GATE codes could calculate DEF for different tissues under irradiation from a low-energy source. National Research and Innovation Agency non 2024-02-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1305 10.55981/aij.2024.1305 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 1-8 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1305/1104 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1305/2415 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1305/2414 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1305/2416 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1305/2417 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1144 2021-06-28T15:53:36Z aij:ACKv47no1

Acknowledgement Atom Indonesia Vol 47 No 1 ack471, ack471 National Research and Innovation Agency 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1144 10.17146/aij.2021.1144 Atom Indonesia; Vol 47, No 1 (2021): April 2021 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1144/902 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1511 2024-09-10T08:58:51Z aij:CVRv50no2

Cover Atom Indonesia Vol 50 No 2 cvr50no2, cvr50no2 National Research and Innovation Agency 2024-08-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1511 10.55981/aij.2024.1511 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1511/1129 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1123 2022-04-12T07:22:29Z aij:ART

In Vitro Release of Metformin HCl from Polyvinyl Alcohol (PVA) - Gelatin Hydrogels Prepared by Gamma Irradiation Hariyanti, H Erizal, E Mustikarani, E. Lestari, I. Lukitowati, F. Gelatin; Hydrogel; PVA; Metformin HCl; Irradiation; Freeze-thaw The aim of this present work is to use polyvinyl alcohol (PVA) – gelatin-based  hydrogel prepared by γ-rays irradiation with different gelatin concentrations ranging from 0.5 - 2 %w/v for immobilization of Metformin HCl (MH) at dose range of 0 - 30 mg. The mixture were freezed-thawed for 3 cycles, irradiated using  γ-rays with sterilization dose at 25 kGy (dose rates 5 kGy/h). Gel fraction and water absorption were determined gravimetrically. The surface morphology of hydrogels were observed using Scanning Electron Microscope (SEM). In vitro release of MH were taken using UV-Vis spectrophotometer. After evaluated, it was found that with increasing gelatin concentrations, gel fraction increases and water absorption decreases. With increasing gelatin concentration and drug dosage, the cumulative drug released decreases. From SEM observation, the hydrogel had a heterogeneous porous. The hydrogel based on PVA-gelatin can be considered as a matrix for controlled drug release and safe for humans since both PVA and gelatin are non-toxic. National Research and Innovation Agency Bonang, IRPASENA BATAN M. Yassin, IRPASENA BATAN 2022-04-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1123 10.17146/aij.2022.1123 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 37-43 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1123/1004 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1123/2129 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1123/2130 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1123/2131 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1123/2132 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1570 2025-08-07T00:44:56Z aij:ART

Safety Assessment of TENORM Waste Landfill on Bangka Island Using Resrad Offsite 4.0 Setiawan, A. Kurniati, M. Iskandar, D. Sucipta, S Pratama, H. A. Setiawan, R. TENORM; Simulation; Resrad offsite; Landfill; Tin slag; Bangka island Bangka Island faced serious environmental challenges due to TENORM (Technologically Enhanced Naturally Occurring Radioactive Materials) waste from tin mining activities. The waste contained radionuclides such as U-238, Th-232, and K-40, which could have had detrimental effects on human health and the environment. To solve this problem, TENORM waste should be disposed of in the class II landfill facility. The Class II landfill was more efficient by cost than the Class I landfill. The landfill design provide a waste contamination layer with dimensions of 160 × 160 × 3 meters. This landfill class has 5 layers from top to bottom cover layers such as the contamination or waste layer, protective coating layer, layer for collecting and transferring, geomembrane layer, soil barrier layer, leak detection system layer, and base layer, which each layer was intended to safeguard against contamination. These protective layers were required to adhere to precise specifications regarding material, thickness, and hydraulic conductivity to effectively manage waste and leachate. Additionally, the base layer consisted of compacted clay, designed to regulate hydraulic conductivity and offer sustained environmental protection. This paper will discuss the radiological safety assessment of this landfill design. This design was modeled using Resrad Offsite 4.0 software to assess its radiation safety in order to fulfill landfill safety requirements. The simulation results showed a maximum radiation dose of 0.40537 mSv per year at a distance of 200 meters from the landfill center, which was estimated to persist for 29,265 years after the landfill was closed. The cancer risk probability was estimated to be 4.25 × 10⁻⁴. More importantly, this dose was still below the safe limit set by BAPETEN (Nuclear Energy Regulatory Agency) for public radiation exposure, which is 1 mSv per year. The class II landfill design, based on the simulation results, was safe for public health and the environment. National Research and Innovation Agency National Research and Innovation Agency IPB University 2025-07-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1570 10.55981/aij.2025.1570 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 119-129 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1570/1173 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1570/2732 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1570/2733 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1570/2734 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1570/2735 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1283 2022-12-23T13:44:38Z aij:PRVv48no3

Preface Atom Indonesia Vol 48 No 3 preface48no3, preface48no3 National Research and Innovation Agency 2022-11-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1283 10.17146/aij.2022.1283 Atom Indonesia; Vol 48, No 3 (2022): December 2022 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1283/1054 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1590 2026-04-02T08:55:18Z aij:ART

Isolation and Selection of Radiation Resistant Fungi from Mamuju High Natural Radiation Soil for Uranium and Thorium Bioremediation Robifahmi, N. Laksmana, R. I. Pratama, A. A. Kusuma, A. T. Tjiptosumirat, T. Tuasikal, B. J. Nugraha, E. D. Rijal, M. S. Febrian, V. A. Yusup, M. Futy, W. Mujiyanto, A. Sugoro, I. Radiated soil fungi; Bioremediation; High nature radiation; Mamuju Microorganisms from high natural radiation environments hold potential as bioremediation agents for radioactive waste. In this study, isolation and selection of fungi from Mamuju high natural radiation soil was done for radioactive bioremediation. The methods included fungal isolation from soil samples, radiosensitivity tests, sensitivity tests to uranium and thorium, and absorption tests under gamma radiation (100 Gy hour-1). Results revealed three fungal isolates with high growth ratios and resistance to gamma radiation: Talaromyces flavus (A3), Gongronella butleri (A4), and Aspergillus sp. (F1). Isolates A3 and A4 survived up to 2 kGy, while F1 endured up to 8 kGy. At 24 hours, A3 absorbed uranium at 96% with a biomass of 0.73 g and thorium at 84% with 0.98 g biomass. A4 achieved the highest uranium absorption of 97% (biomass 4.11 g) and thorium absorption of 100% (biomass 0.74 g). F1 demonstrated 96% uranium absorption (biomass 1.29 g) and 87% thorium absorption (biomass 2.17 g). These isolates exhibited significant potential for bioremediation of uranium and thorium-contaminated environments, showing unique adaptations to high radiation conditions and effective radioactive metal uptake. National Research and Innovation Agency 2026-04-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1590 10.55981/aij.2026.1590 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 93-102 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1590/1211 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2606 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2923 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2924 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2925 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2926 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2943 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1590/2944 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/899 2020-09-25T01:30:16Z aij:ART

Comparison of Gamma Index Passing Rate in Several Treatment Planning System Algorithms Liura, S. Pawiro, S.A. Dose calculation algorithm; Gamma index analysis; Passing rate; TPS The verification of dose calculation algorithm in a new Treatment Planning System (TPS) can be evaluated by comparing the passing rate of the gamma index analysis of the evaluated algorithm and the clinically implemented algorithms. In the present investigation, the gamma index passing rates was investigated as the reference data in the verification of the new three-dimensional TPS. The algorithms which are used in this study are Pencil Beam Convolution (PBC) version 11.0.31 and Anisotropic Analytical Algorithm (AAA) version 11.0.31 in Eclipse v.11 TPS, and Fast Convolution (FC), Adaptive Convolution (AC), and Collapsed-Cone Convolution (CCC) in Pinnacle3 v.7.6c TPS. The 6 MV X-ray beam configurations were varied in the depth of measurement points, field sizes, source-to-surface distances, and wedge angles. The dose measurement was done using MatriXX Evolution and PTW 2D-array seven29. Then, OmniPro ImRT and Verisoft 3.1 software were chosen to analyze the gamma index from varied gamma criteria (3 %/3mm, 2 %/3mm, 3 %/2mm, and 2 %/2mm). Overall, the passing rate of AAA is the highest rate obtained of all algorithms. For gamma criterion of 2 %/2mm, the passing rate of AAA was 93.18 % ± 7.21 %, the passing rate of PBC was 89.76 % ± 7.21 %, and the passing rate of convolution algorithms was 76.84 % ± 11.10 %. National Research and Innovation Agency Universitas Indonesia 2020-08-11 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/899 10.17146/aij.2020.899 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 77-84 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/899/839 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1212 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1218 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1304 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1570 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1571 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1676 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1677 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1703 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1838 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1839 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1840 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/899/1841 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1288 2023-12-19T03:11:18Z aij:ART

Uncovering the Distribution Zones of Uranium and Thorium in Bangka Island Ngadenin, N Fauzi, R. Syaeful, H. Widana, K. S. Sukadana, I. G. Indrastomo, F. D. Widodo, W Uranium; Thorium; Radiometry; Mineralogy; Radioactive mineral; Bangka Radioactive minerals, especially containing uranium and thorium, can be used as a core element of nuclear fuel. Bangka Island is located in The Southeast Asian Tin Belt where it has a large uranium and thorium potential. The purpose of this study is to delineate distribution zone of uranium and thorium in Bangka Island. The study methods consist of radiometric measurement and mapping, petrographic analysis, and mineralogical analysis of pan concentrate samples. Based on radiometric measurement, positive anomaly value of equivalent uranium (eU) is ranging from 5-15 ppm while of equivalent thorium (eTh) is ranging from 45-75 ppm. The result of petrographic analysis from several outcrops of Klabat Granite indicated that there are monazites found in several samples of Mangkol Granite and of Bebuluh Granite. Radioactive mineral indication also can be identified as pleochroic halo within biotite in samples of Pelangas Granite and Menumbing Granite. Based on the result of mineralogical analysis of pan concentrate samples, it was identified that monazites can be found in all samples. Monazites constitute the percentages ranging from 2.82-10.66 %. Zircon also can be identified with percentages ranging from 9.13-76.75 % while ilmenite and magnetite minerals have average percentages of 24.09 % and 5.97 %, respectively. Favorable zones can be delineated in outcrops of Klabat Granite, Ranggam Formation and alluvial deposits in northern, northwestern, northeastern, central, and southeastern parts of Bangka Island. The occurrences of monazites in those lithological units are the main factors of high radioactivity in Bangka Island. Based on petrographic and mineralogical composition, those granite bodies which are correlated with Klabat Granite are mostly associated with ilmenite series with S-Type granitic rocks. National Research and Innovation Agency National Nuclear Energy Agency (BATAN) Research Organization for Nuclear Energy – National Research and Innovation Agency (OR TN-BRIN) 2023-12-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1288 10.55981/aij.2023.1288 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 177-184 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1288/1095 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2354 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2355 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2356 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2357 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2364 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1288/2365 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1352 2024-09-10T08:58:51Z aij:ART

Carbone or Oxygen Therapy: A Comparative Dosimetric Study Using PHITS Code El Bekkouri, H. Al Ibrahmi, E. El-Asery, M. Bardane, A. El Mahjoub, C. Didi, A. Sadoune, Z. Hadrontherapy; PHITS code; Oxygen ion; Carbon ion; Bragg curve Compared to conventional radiotherapy (X-rays or γ-rays), charged particle therapy shows more potential in treating deep-seated and radio-resistant tumors. Currently, all centers that offer hadron therapy use proton or 12C ion. Ongoing research is exploring the possibility of using others heavier ions, such as oxygen ion 16O or helium ion 4He. In this study, Monte Carlo method was used employing the Particle and Heavy Ion Transport code System (PHITS), to examine the amount of dose deposited by incident particles of 12C ion with energies of 200 and 300 MeV/u, as well as 16O ions with energies of 237.5 and 358.5 MeV/u. In this study, we investigated the depth dose distribution of carbon and oxygen ion beams by comparing their energy deposition in a water phantom and the impact of secondary particles. When considering lower energies, oxygen ions are more advantageous than carbon ions as they have slightly higher peak input ratios. This property enables higher doses to be delivered to tumor targets or lower doses to healthy surrounding tissues. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1352 10.55981/aij.2024.1352 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 135-141 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1352/1120 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2443 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2486 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2487 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2488 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2489 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2490 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1352/2491 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1149 2021-12-09T05:47:53Z aij:ART

Natural Radioactivity and the Evaluation of Related Radiological Risks in Concrete Used in Prizren District, Kosovo Qafleshi, M. Xhixha, M. K. Nafezi, G. Kryeziu, D. Qafleshi, D. Natural radioactivity; Activity concentration; Radiological risks; Concrete This study aims to investigate the natural radioactivity levels in concrete made of Portland cement and used in Prizren district, Republic of Kosovo. The activity concentrations of 40K, 226Ra and 232Th were determined by gamma-ray spectroscopy technique with High Purity Germanium (HPGe) detector. The activity concentrations of 40K, 226Ra, and 232Th were found to be 15.4-28.4 Bq kg-1, 4.3-5.9 Bq kg-1 and 2.0-4.1 Bq kg-1, respectively. These results were used to calculate the activity concentration index as recommended by the Basic Safety Standard of Council Directive 2013/59/EURATOM for the safe use of building material. Kosovo must comply with this recommendation in the framework of legislative harmonization with the European Union. The activity concentration index was found to be lower than the reference level of unity (I=0.05), corresponding to an annual effective dose rate of AED=0.05 mSv y-1. The concentration of radionuclides and radiological hazard parameters for concrete investigated in this study were compared with respective results found in literature from different countries. These results show very low activity concentrations, indicating that concrete used in Prizren, Kosovo, does not pose any significant risk due to its use as building material. National Research and Innovation Agency 2021-12-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1149 10.17146/aij.2021.1149 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 227-232 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1149/999 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1149/2018 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1149/2090 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1149/2091 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1149/2092 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1149/2093 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1181 2025-04-14T03:30:31Z aij:ART

Heavy Metal Waste Using Ch/AgNPs Synthesized by Gamma Radiolysis: Preliminary Study Ariyanti, D. Basuki, K. T. Megasari, K. Ismail, I Abimanyu, A. Hamadi, H. Rozana, K. AgNPs/chitosan; Gamma irradiation; Sensitivity; Detection; Heavy metal Environmental issues had always been a problem for all countries in the world. Within a certain threshold, heavy metal waste in water and air must be considered. Various methods and instruments could be used for analysis of heavy metal waste levels. However, quick and accurate method needs to be upgraded in order to improve the efficiency of analysis. Ag nanoparticle is an alternative that could be used to detect the presence of heavy metal waste. Ag nanoparticles can be synthesized through reduction reaction with reductant agents from chemicals, biological compounds, and gamma irradiation. This research used qualilative analysis, utilizing chitosan stabilizer for Ag nanoparticles with gamma irradiation reductant in various doses, such as 7.5, 15, and 20 kGy. The results showed that AgNPs/chitosan was formed in the peak absorption range of 390-500 nm with optimum gamma irradiation dose of 15 kGy. In addition, AgNPs/chitosan has good sensitivity to detect Cr and Hg metals and was not sensitive to Cu and Pb metals. National Research and Innovation Agency Polytechnic Institute of Nuclear Technology 2025-03-17 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1181 10.55981/aij.2025.1181 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 63-69 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1181/1159 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1181/2651 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1181/2652 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1181/2653 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1181/2654 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1233 2022-12-22T17:40:30Z aij:ART

Efficient and Practical Radiosynthesis of Novel [131I]-Xanthine and [131I]-Hypoxanthine Wongso, H. Nuraeni, W. Rosyidiah, E. Xanthine; hypoxanthine; labeling; iodine-131; natural products Natural products (NPs) have been the basis for the discovery and development of pharmacologically relevant drug-related molecules, including radiopharmaceuticals. Xanthine (3,7-dihydropurine-2,6-dione) and hypoxanthine (1,9-dihydro-6H-purin-6-one) are purine-based natural heterocyclic alkaloids that are generally found in some plants, animals, and the human body (e.g., muscle tissue, blood, and urine). The purpose of this study was to label xanthine and hypoxanthine with radioactive iodine-131 (a theranostic radionuclide) by a direct labeling method using chloramine-T as an oxidizing agent. Several experiments were performed to optimize the labeling efficiency by changing reaction conditions, including the ratio of starting material and chloramine-T, pH, solvent, temperature, and reaction time. Overall, labeling at acidic conditions in dimethyl sulfoxide (DMSO) resulted in considerable low radiochemical yields (RCYs) ( 4.0 %), and therefore the focus was shifted to exploit the alkaline reaction conditions. The optimized reaction condition: pH (10.5-11.0), xanthine:chloramine-T ratio (1:2), reaction temperature (27 ºC), and reaction time (30 min),  provided [131I]-xanthine with a RCY of 65.8 ± 0.1 %. After purification with extraction using chloroform (CHCl2), the radiochemical purity (RCP) of 95.1 % was achieved, as indicated by radio-thin layer chromatography (radio-TLC) analysis. In addition, the labeling of hypoxanthine was accomplished in a maximum 60.3 ± 0.2 % RCY, and after purification a RCP of 94.2 % was obtained. The present results provide an efficient and practical labeling method for xanthine and hypoxanthine with iodine-131, suggesting that these radiolabeled compounds can be further investigated in in vitro and in vivo studies for their theranostics potential. National Research and Innovation Agency National Research and Innovation Agency of Indonesia 2022-11-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1233 10.17146/aij.2022.1233 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 185-191 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1233/1035 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2185 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2186 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2182 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2177 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2178 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2179 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1233/2180 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1768 2026-04-02T08:40:57Z aij:ART

Application of Sub-Miniature Fission Chamber Neutron Detector for Neutron Flux Measurement at the RSG-GAS Reactor: Foil Activation Benchmarking Gusman, R. Agung, A. Subekti, R. M. Iswahyudi, F. N. Susanti, F. Pinem, S. Sub-miniature fission chamber; Thermal neutron flux; Gold foil activation; RSG-GAS reactor Accurate neutron flux measurement is essential for reactor characterization and utilization. At the RSG-GAS reactor, previous flux measurements relied on the foil activation method. While this method provides high accuracy, it lacks real-time capability due to its requirement for irradiation, post-irradiation cooling, and subsequent gamma spectroscopy for activity assessment. Direct online measurements of thermal neutron flux in the RSG-GAS reactor irradiation positions were performed using a Sub-Miniature Fission Chamber (SMFC) detector, where the flux was determined from the detector's output current proportional to fission events. This approach offers a viable alternative to the conventional foil activation technique by eliminating its time-consuming process and multiple uncertainty sources. After applying a correction factor obtained from gold foil activation reference measurements and the combined measurement uncertainty was quantified as ± 4.0%, results showed an axial flux distribution peaking at 200 mm height from the bottom of the core with maximum values of 4.997 x 1012 ± 0.199 x 1012 n/cm².s at central iradiation position (CIP E7), 6.212 x 1012 ± 0.248 x 1012 n/cm².s at iradiation position (IP B6), and 2.096 x 1012 ± 0.083x1012 n/cm².s at reflector element with plug (BS+ A2) under 200 kW operation. Radial mapping at 600 mm height from the bottom of the core revealed a maximum flux of 1.230 x 1012 ± 0.049 x 1012 n/cm².s at IP (G7). These results demonstrate that the Sub-Miniature Fission Chamber (SMFC) enables real-time neutron flux monitoring and provides a viable alternative to the conventional foil activation technique. National Research and Innovation Agency National Research and Innovation Agency (BRIN) 2026-02-26 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1768 10.55981/aij.2026.1768 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 1-13 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1768/1202 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1768/2813 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1768/2898 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1768/2899 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1768/2900 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1768/2901 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1324 2023-06-03T02:47:20Z aij:PRVv49no1

oai:ojs.aij.batan.go.id:article/1279 2023-08-29T02:15:31Z aij:ART

Radon Concentration in Urban Areas in the North and West of Morocco Tayebi, A. El-Maghraoui, M. Tayebi, M. El-Mahjoub, C. Radon; Emanation; Dosimetric; Urban environment; Carcinogenic Radon is a colorless, odorless radioactive gas produced by the decay of uranium and radium. It is the second cause of cancer of the lungs after smoking. It has been present in Earth's crust since the creation of Earth. Uranium-rich rocks in the deep crust are the main source of radon. Its emanation from the ground surface varies from one point to another depending on the physical characteristics of the terrain crossed as observed in this study between North and West Morocco. A dosimetric study of those emanations was performed by using the LR-115 solid-state nuclear track detector (SSNTD) which was subsequently processed by techniques developed and calibrated in the laboratory. The study revealed high concentrations of this gas in confined spaces at ground level and, in particular, in basements and less-ventilated ground floor rooms. In order to reduce these concentrations of radon and the probability of carcinogenic attacks by these accumulations of this gas, it is recommended to ventilate these premises well. Good air circulation allows the removal of this harmful gas. National Research and Innovation Agency 2023-08-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1279 10.55981/aij.2023.1279 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 131-135 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1279/1084 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1279/2325 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1279/2330 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1080 2021-06-28T15:53:36Z aij:ART

Calculated Electronic Energy Loss of Heavy Ions at Low Energies in LR-115, Kapton, SiO2, and Al2O3 Amorphous Materials El Asri, J. El Bounagui, O. Tahiri, N. Chetaine, A. Erramli, H. Electronic stopping power; Modified LSS theory; Heavy ions; Polymeric foils The electronic stopping powers of LR-115 and Kapton polymeric foilshave been estimated, using Monte Carlo simulations, for 9Be, 11B, 12C, 14N, 16O, and 35Cl ions covering the energy range ~0.1-1.0 MeV/n. Comparison of stopping power based on Lindhard, Scharff, and Schiott (LSS) theory with the corresponding values obtained by SRIM and MSTAR codes in LR-115 and Kapton polymeric foils illustrate a significantly large deviations. However, a semiempirical equation has been proposed here and tested for better stopping power calculations at low-energy regime in the domain of LSS theory for Z = 4-8 ions across materials. Furthermore, the electronic energy losses for 9Be and 16O ions in SiO2 and Al2O3, respectively, have been calculated in the energy range of ~0.1-1.0 MeV/n. The calculated stopping powers exhibit up to 10 % deviation from the experimental values and MSTAR data. National Research and Innovation Agency 2021-04-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1080 10.17146/aij.2021.1080 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 17-23 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1080/892 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1080/1965 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1080/1966 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1080/1967 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1080/1968 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/947 2021-12-10T07:09:31Z aij:ART

Characterization of The Heat Transfer on Spray Quenching for Different Material Properties Sabariman, S Specht, E. Spray quenching;Boiling regime;Leidenfrost temperature;DNB temperature;Maximum heat flux A broad range of water spray applications as a means of two-phase cooling scheme has encouraged researches in the thermal management system to support safety and process efficiency in industries. In the application of above saturation temperature, the cooling process follows the boiling curve where the dissipated heat flux is figured out as a function of the wall temperature. Knowledge on constructing the boiling curve is an essential part in order to define the moving boundary, and boundary value problems occur in metal cooling process analysis involving heat transfer and phase change. The objective of the research was to characterize the boiling parameters on different materials in the regime of film boiling, transition boiling, and nucleate boiling as the basis for its boiling curve construction. To explain the influence of material properties, this work is featuring, firstly, the calculated vapor film thickness in film boiling regime by promoting self-developed analytical model of single droplet and, secondly, the calculated boiling width which indicates a strong combination of surface temperature and heat flux observed as the boiling phenomena. This is obtained by calculating the propagation of wetting front and 100 oC points. This experimental work employed a volumetric spray flux of 4.2, 10 and 13.7 kg/m2s to cool a hot metal samples of aluminum alloy AA6082 and nickel heated up to 560 °C. An infrared camera was used to record the temperature drop over time. Heat flux calculation follows the numerical procedure according to 1D energy balance model. Calculated vapor film thickness explains why the HTC tends to increase with the decrease of the surface temperature. Leidenfrost and Departure from Nucleate Boiling (DNB) temperatures are found to be inversely proportional to the heat penetration coefficient of the metal while maximum heat flux and boiling width increase with it. National Research and Innovation Agency Institute of Fluid Dynamics and Thermodynamics, OvGU, Germany 2021-11-03 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/947 10.17146/aij.2021.947 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 153-162 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/947/987 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1601 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1745 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1816 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1826 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1875 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1926 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/1928 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/2061 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/2062 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/2063 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/947/2064 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1573 2024-12-03T02:00:48Z aij:CVRv50no3

Cover Atom Indonesia Vol 50 No 3 Indonesia, Atom National Research and Innovation Agency 2024-09-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1573 10.55981/aij.2024.1573 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1573/1149 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1082 2022-08-22T00:27:11Z aij:ART

Potentials of Alginates as Capping Agent for Oral Colon Delivery of Radiosynthesized Silver Nanoparticles: A Review Perkasa, D. P. Arozal, W. Suhaeri, M. AgNPs; Alginate; Capping agent; Nanomedicine; Oral colon delivery; Radiosynthesis Radiosynthesized silver nanoparticles (AgNPs) offer benefits for treatment of chronic colon inflammation due to their anti-inflammatory activity. Targeted delivery of AgNPs to the colon allows topical treatment at high concentration but at reduced systemic side effects. Meanwhile, related to drug administration, oral route is a common method. However, the physiology of the gastrointestinal (GI) tract limits the AgNPs ability to achieve their therapeutic level. This is specifically related to the acidic environment of the stomach and mucus layer of the GI tract. Concurently, alginates are one of the most extensively explored biomaterial classes for drug delivery system due to its biocompatibility, gel-forming ability at mild condition, anionic nature, sensitivity, and mucoadhesiveness. In this review we provide an overview of appropriate features of alginates as capping agent for oral delivery of radiosynthesized AgNPs to the colon. As capping agents, alginates play multiple roles specific to its processing stages, i.e., radiosynthesis, stabilization of nanoparticle system, and oral colon delivery devices of AgNPs. Additionally, we describe outstanding features of alginates as capping agents for drug delivery device as well as the positive contributions of radiation processing on improving the functional effects of alginate. National Research and Innovation Agency Universitas Indonesia National Nuclear Energy Agency Kemenristek/BRIN 2022-08-18 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1082 10.17146/aij.2022.1082 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 125-136 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1082/1024 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1587 2026-02-26T03:01:50Z aij:ART

Comparison of Lung Cancer Lesion Detection Capability on Standard Dose and Low Dose Computed Tomography Capabilities: An In-House Phantom Study Hutami, A. K. Raharja, H. D. R. Lubis, L. E. Soejoko, D. S. Low-dose computed tomography; Phantom in-house; Signal Difference to Noise Ratio; Figure of Merit; Noise Power Spectrum The use of Low-Dose Computed Tomography (LDCT) protocols has garnered significant attention, particularly in detecting cancerous lesions in high-risk populations. However, the drawback of low-dose CT protocols results in image noise. Solutions introduced, such as the use of reconstruction techniques, tend to be time-inefficient, complex, and costly. This paper aims to explain the design and construction of an approach for evaluating the quality of lung cancer lesion imaging that is adequate and easily implementable. In this study, a custom-designed in-house phantom is required to simulate lung cancer lesions. The in-house phantom was constructed from organ or tissue-equivalent materials and equipped with various Hounsfield Unit values and lesion diameter sizes, which were determined based on data from 73 patients, consisting of both males and females, using contrast. Scans were performed on the phantom using standard-dose and low-dose protocol parameters. The results demonstrated that the low-dose protocol was able to detect small lesions at lower radiation levels. The contrast difference is quite good with a Signal Difference to Noise Ratio (SDNR) value ≥ 5. The image was optimum with a relatively high Figure of Merit (FOM). Additionally, Noise Power Spectrum (NPS) measurements provided accurate results within a specific range of spatial frequencies. National Research and Innovation Agency 2025-10-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1587 10.55981/aij.2025.1587 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 221-228 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1587/1188 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1587/2825 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1587/2826 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1587/2827 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1587/2828 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1335 2023-06-03T02:55:28Z aij:ACKv49no1

Acknowledgement Atom Indonesia Vol 49 No 1 ack49no1, ack49no1 National Research and Innovation Agency 2023-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1335 10.55981/aij.2023.1335 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1335/1075 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/984 2020-12-16T02:45:17Z aij:ART

Molecular and in silico Study of TP53 Codon 72 Polymorphism (rs1042522) in a Population Exposed to High Background Radiation in Mamuju-West Sulawesi Tetriana, D. Purnami, S. Rahardjo, T. Mailana, W. Nurhayati, S. Pudjadi, E. Widyaningtyas, S. Tri Ishida, T. Ramadhani, D. In silico; Mamuju; Polymorphism; Radiation; TP53 The evaluation of the tumor protein p53 (TP53) codon 72 polymorphism (rs1042522) status in a population exposed to high background radiation was performed in this study. Real-time polymerase chain reaction (Q-PCR) was used to genotype the rs1042522 polymorphism in 100 subjects from Takandeang, Salleto, and Ahu villages in Mamuju district, West Sulawesi. An in silico study was then conducted to identify the potential effects of the proline substitution associated with this polymorphism on protein stability. The in silico analysis was performed using three different computational tools, namely I-Mutant Suite, iStable, and Protein Variation Effect Analyzer (PROVEAN). Secondary and three-dimensional (3D) structural models for wild-type (WT) and variant TP53 were generated to predict potential structural changes in the protein. Electrostatic surface charge calculations were also performed to identify changes in the electrostatic charge of codon 72. The Pro72 and Arg72 frequencies among the inhabitants in the Takandeang, Salleto, and Ahu villages, who are Mandarese Austronesian-speaking ethnic group members, were 0.56 and 0.44, respectively. The in silico analysis revealed no negative effects on protein stability due to the proline substitution at codon 72, although molecular modeling showed several differences in the secondary and 3D structures of the TP53 variant compared with the structure of WT TP53. To determine the impact of the proline-coding allele on individual sensitivity to radiation exposure, we compared the micronucleus (MN) frequencies of each genotype. The results showed that the MN frequencies in individuals harboring the proline-coding allele were not significantly higher than those expressing the arginine-coding allele. In conclusion, this study revealed that the proline-coding allele for codon 72 of the TP53 gene represented the predominant genotype among Takandeang, Salleto, and Ahu villages inhabitants. The present study also demonstrated that individuals who carried the proline-coding allele were not more sensitive to radiation compared with those expressing the arginine-coding allele for codon 72 of the TP53 gene. National Research and Innovation Agency National Nuclear Energy Agency 2020-12-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/984 10.17146/aij.2020.984 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 163-169 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/984/865 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1623 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1624 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1760 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1761 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1823 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1876 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1877 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1878 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/984/1879 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1307 2024-04-16T02:55:07Z aij:ART

Weighted CTDI Equation for 3D Rotational Angiography: A Monte Carlo Study Azzi, A. Hidayat, R. Rosa, A. Lubis, L. E. 3D rotational angiography; CTDI; Monte Carlo; CBCT This study aims to verify the weighted Computed Tomography Dose Index (CTDIw) coefficients of 3D rotational angiography (3DRA) procedure using Monte Carlo simulation. The Monte Carlo simulation EGSnrc usercode was employed for 3D dose simulations of the rotational angiography procedure. A virtual phantom resembles the head CTDI phantom was constructed, with a diameter of 16 cm and a density resembling polymethyl methacrylate (1.13 g/cm3). A series of virtual phantoms consisting of 5 images with ionization chamber detectors at the center position, 12 o'clock, 9 o'clock, 6 o'clock, and 3 o'clock were acquired. Simulations were performed with photon sources of 70 and 109 kVp for 200-degree x-ray tube rotation. The field of view was divided into narrow, wide, and full beam with diameters of 1.7 cm; 4.9 cm; and 8.6 cm, respectively. The simulated doses at the ionization chamber were processed into weighting factor for weighted CTDI and compared with direct measurements. The dose ratio between peripheral and center positions for 360° CBCT and 200° 3DRA was 1:1 and 1:3 in this study. The weighting factors for 3DRA were determined as CTDIcenter = ¼ and CTDIperiphery = ¾. The measured average percentage difference of CTDIw between our weighted factor and conventional CTDIw was 1.75 % (-3.99 % to 6.08 %). The x-ray tube position of 3DRA impacted the accuracy of weighting factor of CTDIw, with implications for the proposed weighting factor (Wcenter = ¼ and Wperiphery = ¾) when using a 3DRA machine. National Research and Innovation Agency 2024-04-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1307 10.55981/aij.2024.1307 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 43-48 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1307/1110 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1307/2392 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1307/2393 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1307/2394 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1307/2395 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1307/2424 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1120 2021-08-30T07:42:43Z aij:ART

Impact of Tube Voltage on Radiation Dose (CTDI) and Image Quality at Chest CT Examination El Mansouri, M. Choukri, A. Talbi, M. Hakam, O. K. During Computed Tomography (CT) scan examinations, it is important to ensure a good diagnosis by providing the maximum information to detect pathologies and this can be done with a reduced dose. In this respect, several methods of dose reduction have been studied and evaluated. This work investigates the effect of tube voltage while varying the tube current on image quality and radiation dose at Chest CT examination. This study was conducted on HITACHI CT 16 slice Scanner using two phantoms for evaluating the dose and image quality; a PMMA phantom and a CATPHAN 500. Two tube voltages of 120 KVp and 100 KVp have been used for some variation of the tube currents (mAs) and recording the values of the measured quantities (CTDIv, spatial resolution, contrast to noise ratio CNR and noise). The scanning with 100 KVp at Chest CT examination led to a reduction in CTDIv until 45 %, an increase of noise from 17 % to 45 %, and the Spatial Resolution fell slightly (6 and 7 pl/cm) compared to the 120 KVp. The CNR shows a slight regression from 11 to 22 % for the 120 KVp and 100 KVp. This study has shown that despite the increase in the image noise at low tube voltage 100 KVp, it is possible to reduce the radiation dose by up to 45 % without degradation of image quality at Chest CT examination. Further works will evaluate the effect of acquisition parameters in other CT examinations. National Research and Innovation Agency 2021-07-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1120 10.17146/aij.2021.1120 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 105-109 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1120/980 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1120/2033 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1120/2034 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1120/2035 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1120/2036 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1120/2037 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1469 2024-12-13T01:08:53Z aij:ART

Radiation Dose Calculation Analysis During The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results El Azzaoui, B. Kabach, O. Outayad, R. Messous, M. Y. Bergaoui, K. Nbaoui, K. Kadiri, J. Chakir, E. Alibrahmi, E. Kharchaf, A. DSRSs; Dismantling; Radiological safety; MCNP; 60Co Disused Sealed Radioactive Sources (DSRS) present significant risks of radiation exposure and environmental contamination during dismantling. Despite their sealed nature, DSRS can emit ionizing radiation, necessitating careful management to mitigate health risks. This article presents the MCNP simulation results of dosimetric operational quantities, namely Hp(3), Hp(10), and H(0.07), for hands and feet. This study focuses on a 60Co source, due to its high radiation energy levels and widespread use in various socioeconomic sectors. The assessment of radiation exposure levels enabled the improvement of occupational radiation protection measures related to critical areas and steps in the dismantling process. According to the obtained results with the 60Co source at its initial activity, and considering the maximum task duration, the dismantling process contributes to approximately 72.35 % of the daily dose limit of 80 µSv for worker category A, for the whole body. Therefore, these findings can contribute to a better understanding of radiation exposure risks and confirm compliance with regulatory requirements. National Research and Innovation Agency 2024-11-12 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1469 10.55981/aij.2024.1469 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 231-238 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1469/1137 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1469/2598 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1469/2599 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1469/2600 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1469/2601 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1238 2022-04-13T13:04:02Z aij:CVRv48no1

Cover Atom Indonesia Vol 48 No 1 cover48no1, cover48no1 National Research and Innovation Agency 2022-03-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1238 10.17146/aij.2022.1238 Atom Indonesia; Vol 48, No 1 (2022): April 2022 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1238/1014 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1647 2025-08-07T00:44:56Z aij:ART

The Dependence of the Rupture Probability on the Mass Number of the Fissionable Nucleus Auliya, Z. Kurniadi, R. Irwanto, D. Rupture probability; Fission yield; SEMF; TALYS The relationship between the mass number of fissionable nuclei and fission yield is generally known through the fission barrier. The deformation energy of the SEMF determines the probability of the formation of fission products. The use of deformation energy is very impractical because it goes through many calculation stages. For this reason, the Neck Rupture Model was introduced, namely a model that shortens the stages of the calculation process through the rupture probability formula. In this paper, a new technique was introduced that adds the dependence of the rupture probability on the mass number of the nucleus that will undergo fission. Apart from this, this technique also obtained better fission yield calculation data compared to the previous technique. The fission yield calculations of Uranium isotopes at an energy of 14 MeV will be shown. National Research and Innovation Agency 2025-08-05 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1647 10.55981/aij.2025.1647 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 173-177 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1647/1178 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1647/2762 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1647/2763 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1647/2764 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1647/2765 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1647/2776 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1214 2023-06-03T02:55:28Z aij:ART

Assessment of Computed Tomography Dose Index (CTDI) During CT Pelvimetry Using Monte Carlo Simulation Aabid, M. Semghouli, S Choukri, A. CT pelvimetry examination; Monte carlo simulation; CTDI; GATE code A pelvimetry examination is sometimes prescribed to a pregnant woman at the end of her pregnancy in order to assess the dimensions of her pelvis prior to childbirth. This examination has long been performed by using X-ray, but is now increasingly being replaced by CT-scan The objective of this study is to assess the radiation doses received during a practical CT pelvimetry examination performed using a Hitashi Supria 16-slice CT scanner. The radiation doses were estimated using Monte Carlo (MC)-based simulation with GATE code to model the 16-slice CT scanner machine. The GATE code operates using GEANT4 libraries. A polyymethyl metacrylate (PMMA) acrylic phantom of 32 cm diameter was modeled to represent the patient's body. X-ray energy spectrum generated using the SRS-78 spectrum processor was used for simulation. The simulation was executed with the same exposure parameters as the practical CT pelvimetry examination with dose parameters of 1 mGy, 0.9 mGy, and 36.6 mGy.cm, respectively, for the weighted CT dose index (CTDIw), the volume CT dose index (CTDIvol), and dose-length product (DLP). The MC simulation results provide dose parameters of 1.16 mGy, 1.07 mGy, and 43.6 mGy.cm, respectively, for the CTDIw, CTDIvol, and DLP. The differences between the simulation and the practical examination were 16 %, 18 %, and 18 %, respectively. These differences are considered in a quite good agreement. The results were also consistent with other similar studies. This work proves that the Monte Carlo simulation with the GATE code is usable to assess the patient doses during a CT pelvimetry examination. National Research and Innovation Agency 2023-03-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1214 10.55981/aij.2023.1214 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 21-25 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1214/1062 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2239 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2235 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2240 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2236 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2237 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1214/2238 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/962 2020-12-29T20:46:27Z aij:ART

Assessment of Levels of Occupational Exposure to UV-A and UV-C Radiation among Shielded Metal Arc Welders in Accra, Ghana Sawyerr, A. Fletcher, J.J. Amoako, J. Sosu, E. Ultraviolet radiation; Radiant exposure; Non-ionizing radiation; Safety standards This study attempted to quantify the irradiance levels of ultraviolet A (UV-A) and ultraviolet C (UV-C) from the shielded metal arc welding (SMAW) process to welders in Accra, Ghana. Exposures were assessed via measurements, observations, and interviews. The assessments were done based on safe exposure levels prescribed by recognized international organizations such as the International Commission on Non-Ionizing Radiation Protection (ICNIRP) and the American Conference of Governmental Industrial Hygienists (ACGIH). Results from the measured UV-C irradiance levels EUV-C ranged between 0.16 ± 0.08 W/m2 and 10.46 ± 1.96 W/m2 with its corresponding permissible exposure duration tmax‑UV‑C per day ranging from 5.74 s to 367.35 s. The measured UV-A irradiance levels EUV‑A ranged from 0.88 ± 0.03 W/m2 to 23.72 ± 6.66 W/m2 with its corresponding permissible exposure duration tmax‑UV‑A per day ranging from 421.59 s to     11,363.64 s. The obtained effective irradiance Eeff has a range of 2.08 W/m2 to 28.79 W/m2 with the range of permissible exposure duration tmax per day of 1.04 s to 14.40 s. It was found that the total exposure time of the welders exceeded the permissible exposure durations and that the safety practices among the welders were unsatisfactory. National Research and Innovation Agency 2020-08-25 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/962 10.17146/aij.2020.962 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 115-124 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/962/844 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1466 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1487 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1499 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1500 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1521 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1700 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1704 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1808 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1862 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1864 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1865 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/962/1866 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1306 2023-12-19T03:11:18Z aij:ART

Temporal Trends and Spatial Relationships of Radioactive Isotopes (I-131, Cs-134, and Cs-137) in Response to Nuclear Events: A Comprehensive Analysis Using Time Series Graphs, Regression, and Multivariate Techniques Nasution, B. Ritonga, W. Doyan, A. Pandara, P. D. Alfaris, L. Siagian, R. C. Radioactive isotopes; Evolution; Longitude and latitude; Linear regression; Principal component analysis (PCA) This research aims to comprehend the evolution of radioactive isotopes      Iodine-131 (I-131), Cesium-134 (Cs-134), and Cesium-137 (Cs-137) over time in diverse locations and analyze their relationships with the independent variables Longitude and Latitude using Linear Regression, Principal Component Analysis (PCA), and Canonical Correlation Analysis (CCA). The data used in this study were processed from the "DE.xlsx" file, including the imputation of missing values with 0 and column transformation into factors. The results of the Linear Regression analysis indicate a significant association between these isotopes and Longitude and Latitude. Additionally, PCA and CCA analyses reveal complex relationships between the isotopes and independent variables. This research provides valuable insights into the historical trends of radioactive isotopes Iodine-131 (I-131), Cesium-134 (Cs-134), and Cesium-137 (Cs-137) in various locations. The novel aspect and uniqueness of this study lie in the utilization of a comprehensive analytical approach, combining Linear Regression, PCA, and CCA to comprehend the relationships between isotopes and specific environmental factors. Moreover, this study significantly contributes to understanding the phenomena of radioactive isotopes and can serve as a foundation for further research in this field. The findings of this research are expected to support efforts in preventing and managing potential environmental and human health impacts of radioactive isotopes in the future. National Research and Innovation Agency Physics Depaertemen, Faculty of Mathematics and Natural Science, Universitas Negeri Medan, Indonesian 2023-12-19 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1306 10.55981/aij.2023.1306 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 215-231 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1306/1100 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1306/2373 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1306/2374 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1306/2375 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1306/2376 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1306/2377 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1075 2021-06-28T15:53:36Z aij:ART

Reactivity Effects in a Very-High-Temperature Pebble-Bed Reactor Pérez, D. M. Pardo, L. H. Pérez, D. M. Garcia, L. P. R. Lorenzo, D. E. M. de Oliveira Lira, C. A. B. Very high temperature reactor; Pebble bed reactor; Reactivity effects; MCNP6; VHTR The very-high-temperature reactor (VHTR) is one of the most promising and innovative designs selected by the Generation IV International Forum. Although previous papers have focused on the study and optimization of several parameter of a VHTR conceptual design, there is still much work needed to achieve the commercial introduction of this technology. The primary aim of this study is to obtain the reactivity effects of such parameters as the temperature of the fuel, moderator, and reflector, and the poisoning by 135Xe and 149Sm in the VHTR critically. To reach this goal, the widely-used MCNP6 code was employed in order to simulate the neutronics of the VHTR. The viability of the utilization of the MCNP6 code and the developed model for the study of the physics of the VHTR core was confirmed through the calculation and comparison with benchmarks provided by the IAEA. Based on the results of the temperature coefficients of reactivity obtained, a negative reactivity effect on the system of about 12 pcm/K was found, as is expected in all the nuclear fission reactors, while the combined effect of fission products 135Xe and 149Sm implies a negative reactivity of 3475 pcm. National Research and Innovation Agency Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq) 2021-04-19 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1075 10.17146/aij.2021.1075 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 55-64 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1075/897 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1828 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1984 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1985 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1986 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1987 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1075/1994 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1411 2024-09-10T08:58:51Z aij:ART

Effects of Patient Dose Reduction Efforts on Image Quality for Thoracic CT in A Moroccan Hospital Saga, Z. Rahmouni, A. Belaroussi, L. Talbi, M. El Mansouri, M. Rezzouk, A. Thoracic protocol; CTDI; PMMA; AAPM phantom; image quality. Thoracic CT imaging is a strongly recommended means of medical imaging. It is accompanied by a high exposure to radiation due to the number of examinations carried out, which requires efforts to reduce the CT dose index (CTDI) while trying to preserve image quality. To this end, this study proposed the possibility of introducing two new imaging protocols for chest tomography. A 16-slice HITACHI SUPIA CT scanner and two phantoms were used to investigate CTDIvol and image quality; the first phantom was made of PMMA and the other of AAPM model 610. Three tube voltages were studied by varying the intensity of the tube current (mA): 120 kVp (120-160-210-230) mA, 100 kVp (160-200-240-290) mA, and 80 kVp (230-260-300-350) mA. The values for noise uniformity and accuracy, contrast-to-noise ratio (CNR), and spatial resolution (SR) were determined using IndoQCT c22a. 92 software. The first thoracic protocol proposed with 100 kVp compared to 120 kVp resulted in a 27.51 % reduction in CTDIvol, a 20 % increase in mA, and a 19.50 % increase in noise. The CNR showed a slight regression of 23.08 %. For the second scan procedure at 80 kVp, the CTDIvol was reduced by 53.32 %, while noise was increased by 53.95 %. There was no statistically significant difference in CNR and SR (p > 0.05) when kVp and mA were reduced compared to the routine protocol. It is suggested that it is possible to adopt two new acquisition protocols at 100 kVp and 80 kVp while reducing the patient exposure dose (CTDIvol) by 28 % and 54 % and taking into account the effect of varying these parameters on image quality. Their choices must be made by integrating and considering clinical issues and a good understanding of the pathophysiology and imaging results of the suspected condition. Consequently, radiologists and technicians should always take a part in improving imaging practices in such a way as to make more effective use of radiation. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1411 10.55981/aij.2024.1411 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 175-182 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1411/1126 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1411/2505 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1411/2506 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1411/2507 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1411/2508 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1411/2509 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1105 2022-04-12T03:55:44Z aij:ART

Skin Dosimetric Comparison of 3DCRT and IMRT Planning for Post-Mastectomy Breast Radiotherapy Hentihu, F. K. Anto, A. K. Nugroho, R. S. 3DCRT; IMRT; Post-mastectomy radiotherapy; Skin dose; Skin-sparing Breast cancer is the most common cancer for incidence and mortality among females globally and in Indonesia. Mastectomy is still the most common surgery for female breast cancer in Indonesia. After the mastectomy, several patients will receive a whole breast radiotherapy session. About 68.75% of breast cancer patients in the radiotherapy department at Lavalette Hospital during 2019 had undergone the mastectomy. Radiotherapy treatment for breast cancer can be delivered using Intensity Modulated Radiotherapy (IMRT) or 3D-Conformal Radiotherapy (3DCRT) technique. This study is aimed to compare the skin dosimetric between IMRT and 3DCRT for post-mastectomy breast radiotherapy. Left-sided breast cancer patients who underwent radiotherapy at Lavalette Hospital during 2019 were included in this study, and 15 patients were selected. All patients received 50 Gy in 25 fractions over 5 weeks using 6 MV photons. The planning target volume (PTV) and organ at risk (OAR) were delineated. Skin with 3 mm thickness along PTV was also contoured for evaluating the dose delivered to the skin. The treatment planning was conducted using 3DCRT and 5 fields IMRT planning. The plans were optimized for at least 95% of the prescribed dose to cover 95% volume of the PTV. The mean dose and maximum dose were used for evaluating and comparing each plan. The skin’s mean dose from 3DCRT planning was 24.65 ± 4.12 Gy and 22.85 ± 3.68 Gy (p = 0.002) for IMRT planning. Meanwhile, skin maximum doses were 54.15 ± 0.68 Gy and 53.89 ± 1.05 Gy         (p = 0.001) respectively for 3DCRT and IMRT planning. These results showed that IMRT offered a lower dose to the skin and a better skin-sparing effect than 3DCRT. National Research and Innovation Agency 2022-03-24 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1105 10.17146/aij.2022.1105 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 9-13 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1105/1007 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2049 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2110 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2111 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2112 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2113 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2114 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1105/2115 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1662 2025-08-06T04:31:44Z aij:PRVv51no1

Preface Atom Indonesia Vol 51 No 1 indonesia, atom National Research and Innovation Agency 2024-12-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1662 10.55981/aij.2025.1662 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1662/1168 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1200 2022-12-22T17:40:30Z aij:ART

Simulation of Dispersion Modeling of 137Cs for the Possible Leakage of Malaysia’s Nuclear Power Plant Operation Muslim, M Maulana, F. I. Suseno, H. Wulandari, S. Y. NPP; Transport Model; Dispersion Model; Radionuclide Spread; 137Cs The world’s energy needs increase in line with population growth. One alternative to overcome this problem is the construction of a nuclear power plant, a source of energy that is cheap, clean, and safe. Malaysia has a plan to construct nuclear power plants by 2025, which is located close to Indonesian waters. This study aimed to determine the distribution model of 137Cs radionuclide released by the nuclear power plant in the event of a leak in east coast of Peninsular Malaysia and its impact on the presence of 137Cs in Indonesian waters. A quantitative method was used in this study with a scenario 2D modeling using hydrodynamics module and transport module in MIKE software. The results showed that the highest concentration of 137Cs would be found in the area around the nuclear power plant with a value of 1011 PBq/m3, then it would decrease through diffusion and advection processes. On the 15th day, the spread of 137Cs would reach Indonesian waters with a distance of up to 76 km and would expand on the 30th day with a distance of up to 130 km from the released source. The movement of 137Cs follows the dominant current pattern due to its nature. The presence of 137Cs in Indonesian waters after the 15th and 30th days would reach a value of 1 Bq/m3 due to advection and diffusion processes. National Research and Innovation Agency Faculty of Fisheries and Marine Science, Diponegoro University 2022-12-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1200 10.17146/aij.2022.1200 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 231-236 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1200/1039 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2187 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2188 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2210 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2211 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2212 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1200/2213 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1724 2026-04-02T08:02:47Z aij:ART

Evaluation of ALON for Proton Shielding of Low Earth Orbit (LEO) Satellite Solar Arrays Firat, C. Proton Radiation Shielding, Aluminum Oxynitride (ALON), Satellite Solar Arrays, SRIM/TRIM Simulations, Satellite Orbits This study evaluates the proton radiation shielding efficacy of various materials, with a focus on ALON, for satellite solar arrays in LEO across the 0.1-200 MeV energy range using SRIM/TRIM simulations. Key metrics, ion penetration, vacancies per ion, range, displacements per atom, non-ionizing energy loss, Bragg curves, and transmission, were analyzed for aluminum, SiO2, polyimide, ALON, and Ta2O5/Al2O3 at thicknesses from 0.01 mm to 4 mm. ALON demonstrates moderate stopping power and damage resistance, with penetration exceeding 20 µm and 100 µm at 0.5 MeV and 5 MeV, respectively, and 2000 µm and 4000 µm providing protection up to 50 MeV and 100 MeV, while maintaining high optical clarity (>80%) for photovoltaic (PV) applications. Thinner layers mitigate high-energy proton damage but are vulnerable to low-energy ( National Research and Innovation Agency 2026-03-17 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1724 10.55981/aij.2026.1724 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 49-61 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1724/1209 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2725 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2932 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2933 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2934 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2935 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2936 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1724/2937 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/141 2022-05-14T23:41:24Z aij:ART

The use of 32P and 15N to Estimate Fertilizer Efficiency in Oil Palm Sisworo, Elsje L. Sisworo, Widjang H. Rasjid, Havid Haryanto, Haryanto Rizal, Syamsul Poeloengan, Z. Martoyo, Kusnu Oil palm; 32P; 15N; N-efficiency Oil palm has become an important commodity for Indonesia reaching an area of 2.6 million ha at the end of 1998. It is mostly cultivated in highly weathered acid soil usually Ultisols and Oxisols which are known for their low fertility, concerning the major nutrients like N and P. This study most conducted to search for the most active root-zone of oil palm and applied urea fertilizer at such soils to obtain high N-efficiency. Carrier free KH232PO4 solution was used to determine the active root-zone of oil palm by applying 32P around the plant in twenty holes. After the most active root-zone have been determined, urea in one, two and three splits were respectively applied at this zone. To estimate N-fertilizer efficiency of urea labelled 15N Ammonium Sulphate was used by adding them at the same amount of 16 g 15N plant-1. This study showed that the most active root-zone was found at a 1.5 m distance from the plant-stem and at 5 cm soil depth. For urea the highest N-efficiency was obtained from applying it  at  two splits. The use of 32P was able to distinguish several root zones: 1.5 m – 2.5 m from the plant-stem at a 5 cm and 15 cm soil depth. Urea placed at the most active root-zone, which was at a 1.5 m distance from the plant-stem and at a 5 cm depth in one, two, and three splits respectively showed difference N-efficiency. The highest N-efficiency of urea was obtained when applying it in two splits at the most active root-zone. National Research and Innovation Agency 2012-10-04 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/141 10.17146/aij.2004.141 Atom Indonesia; Vol 30, No 1 (2004): January 2004; 1-8 2356-5322 0126-1568 10.17146/aij.2004.%a eng https://atomindonesia.brin.go.id/index.php/aij/article/view/141/103 Copyright (c) 2016 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1285 2023-12-19T03:11:18Z aij:ART

Determination of the Diagnostic Reference Level (DRL) in Samarinda Hospitals Jannah, R. Munir, R. Putri, E. R. Abdomen; CT-Scan; Diagnostic Reference Level (DRL); Head; Thorax The diagnostic reference level (DRL) is a form of investigative level used as a tool to help optimize protection to radiation exposure for diagnostic and interventional procedures. The purpose of this study was to determine the local DRL values for the examination of the abdomen, thorax, and head at radiology installations. The modality used was 128-slice CT scan. The numbers of patients whose data were used were 200 for abdominal examinations, 160 for thoracic examinations, and 100 for head examinations. Overall, the total patient whose data was used was 460. Data processing in this study was carried out with a quantitative analysis technique, namely descriptive statistics. This analysis technique used secondary data obtained from the results of recaptures or archival books for examination of the abdomen, thorax, and head. Data processing was carried out with a measure of diversity through the calculation of the third quartile in the data distribution. It was assumed that 75 % of patients performed examinations with a common diagnosis. The results of these calculations are visualized in the form of graphs of the relationship of computed tomography dose index volume (CTDIvol) with the number of patients and a graph of the relationship of dose length product (DLP) with the number of patients. In the abdominal examination, a CTDIvol of 12 mGy and a DLP of 1545.5 mGy·cm. In the thoracic examination, a CTDIvol of 11 mGy and a DLP of 903 mGy·cm were obtained. For the head examination, a CTDIvol of 34.25mGy and a DLP of 2190.25 mGy·cm were obtained. The conclusion obtained from this study is that the DRLs are relatively low, but they still need to be optimized by medical physicists. National Research and Innovation Agency 2023-11-23 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1285 10.55981/aij.2023.1285 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 145-150 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1285/1092 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1285/2349 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1448 2024-04-05T11:28:32Z aij:CVRv50no1

Cover Atom Indonesia Vol 50 No 1 Yusuf, Anggiana Rohandi National Research and Innovation Agency 2024-02-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1448 10.55981/aij.2024.1448 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1448/1115 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1046 2021-12-16T08:39:59Z aij:ART

Monte Carlo Simulation-Based BEAMnrc Code of a 6 MV Photon Beam Produced by a Linear Accelerator (LINAC) Sapundani, R. Ekawati, R. Wibowo, K. M. Monte Carlo simulation; phase-space file; BEAMnrc code; DOSXYZnrc code In radiotherapy, high energy ionizing radiation, such as X-rays, gamma rays and electron beams,is used. The dose in the tissue is often approached with the dose in the medium of the body which is 80 % of human soft tissue. It is often difficult to determine the dose because the interaction of materials in a medium is very random. Measurement is also quite difficult because there are almost no detectors that are tissue equivalent. Measurement using an ion chamber requires a lot of correction to obtain a dose in the tissue, which is done using phantom and not directly in humans. This research aimed to compare the absorbed dose between modelling using Monte Carlo simulation and experiments.  The simulation of dose distribution produced by a 6 MV medical linear accelerator has been performed using BEAMnrc code running on Linux-based 2 processor system arranged in parallel.BEAMnrc was used to model and simulate the linac head with an SSD of 100 cm and Field size of10x10 cm2. A phase-space file is obtained as input to a DOSXYnrc code to produce Percent Depth Dose (PDD) in water and polymethyl methacrylate (PMMA) phantoms. New particles formed (electrons: 0.2 %, photon: 0.17 %; and positron: 0.08 %) were far from the contamination threshold of 2 %. The range of the correction factor of the depth of a maximum dose compared to the experimental data was 0.04-0.15. National Research and Innovation Agency 2021-12-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1046 10.17146/aij.2021.1046 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 199-204 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1046/994 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1046/1813 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1491 2025-04-14T03:30:31Z aij:ART

Radial Sensitivity of the Nuclear Shell Structure at N=92 Swain, R. R. Anupam, A. Mohanty, P. Jena, K. K. Agarwalla, S. K. Sahu, B. B. Improved mass formula; rms charge radius; Shell structures; Deformation The nuclear ground-state properties of Sm isotopes are calculated and analyzed using an improved mass formula. The asymmetric energy term is consistently observed, separated into a volume and surface component. While distinctive signatures for certain isotopes remain elusive, the results show reasonable agreement with experimental data and well-established theoretical models such as the Relativistic-Continuum-Hartree-Bogoliubov (RCHB) and the Finite Range Droplet Model (FRDM). By utilizing a root-mean-square (rms) charge radius formula that incorporates both shell and deformation effects, the study provides new insights into the anomalous shifts observed in magic isotopes (N=82, N=126), as well as in N=92, 136, and 144 within the isotopic series of the "Sm" element. National Research and Innovation Agency KIIT Deemed to be University 2025-02-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1491 10.55981/aij.2025.1491 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 35-41 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1491/1152 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1491/2635 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1491/2636 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1491/2637 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1491/2638 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1491/2639 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1270 2022-08-29T23:07:34Z aij:PRVv48no2

Preface Atom Indonesia Vol 48 No 2 preface48no2, preface48no2 National Research and Innovation Agency 2022-07-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1270 10.17146/aij.2022.1270 Atom Indonesia; Vol 48, No 2 (2022): August 2022 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1270/1031 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1708 2026-02-26T03:01:50Z aij:ART

Evaluation of Neutron Flux in Boron Neutron Capture Therapy for a 10-Year-Old Child with Head and Neck Rhabdomyosarcoma Using Monte Carlo Simulation Salim, F. M. Hidayanto, E. Setiabudi, W. Arianto, F. BNCT; Flux neutron; Head and neck rhabdomyosarcoma; Monte carlo; MCNP 6.2 Head and neck rhabdomyosarcoma is among the most frequently encountered malignancies in children under the age of 10, necessitating effective treatment modalities with minimal toxicity. Boron Neutron Capture Therapy (BNCT) is recognized as a promising therapeutic alternative in radiotherapy owing to its ability to selectively target malignant cells. The aim of this study was to evaluate the neutron beam quality of a BNCT collimator in a simulation model for the treatment of head and neck rhabdomyosarcoma in a 10-year-old pediatric phantom, using the MCNP 6.2 Monte Carlo method. The simulation included tumor modeling incorporating Gross Tumor Volume (GTV), Clinical Target Volume (CTV), and Planning Target Volume (PTV) to assess neutron flux distribution. The results showed a thermal neutron flux of 5.22 × 10⁹ n cm⁻² s⁻¹, an epithermal neutron flux of 1.22 × 10¹⁰ n cm⁻² s⁻¹, and a fast neutron flux of 5.91 × 10⁷ n cm⁻² s⁻¹. Further analysis indicated that the produced epithermal flux exceeded the minimum standard recommended by the IAEA, and the highest flux was concentrated in the GTV region, suggesting effective tumor targeting. However, the thermal-to-epithermal neutron flux ratio (0.43) remained above the threshold value recommended by the IAEA (≤ 0.05). In conclusion, while the collimator design was capable of delivering a high-quality epithermal neutron beam that selectively targeted the tumor, further optimization of the filter components remains necessary to reduce unwanted thermal flux and enhance therapeutic safety and efficacy. National Research and Innovation Agency 2025-12-09 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1708 10.55981/aij.2025.1708 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 273-278 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1708/1197 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2698 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2870 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2871 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2872 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2873 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1708/2874 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1320 2023-04-27T03:24:05Z aij:CVRv49no1

oai:ojs.aij.batan.go.id:article/1152 2023-08-29T02:15:31Z aij:ART

Ʌ-Hypernuclear States as Dihadronic Molecules Jahanshir, A. Constituent masses; Hyperons; Exotic molecules; Hypernuclei; Hadron The study of exotic hypernuclei attracts a great deal of interest in nuclear physics. The reality of heavy hyperon hypernuclei is the subject of intense concern among theoreticians and experimenters in recent years. The core-hyperon model uses to explain abnormal nuclei spectra, recent observations of new exotic heavy hyperon hypernuclei cannot be explained or predicted by ordinary heavy core nuclei. These exotic hypernuclei states are a two-cluster bound states. We calculate the mass spectrum and constituent mass of particles in hypernuclei using the relativistic Schrödinger equation with molecular pseudoharmonic-type potential between particles inside the core and hyperon. Such calculations represent the interaction between the hyperon and the nuclei core. I review recent theoretical studies on the ground states and the excited states of hypernuclei bound states. Finally, we present explicit predictions of the exotic bound states based on the interactions obtained from quantum field theory and the projective unitary representation model. Studies have shown that by increasing the mass number of hyperon-core states,  the value of the constituent mass and energy eigenvalue of Ʌ-hypernucleus increases. Also, by growing and increasing the proton number in the (Ʌ-N) states the value of the constituent mass of Ʌ-hyperon increases. National Research and Innovation Agency 2023-08-06 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1152 10.55981/aij.2023.1152 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 103-108 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1152/1082 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2021 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2022 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2023 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2242 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2243 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2302 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2303 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2304 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2305 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2309 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1152/2316 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1109 2020-12-23T05:16:04Z aij:ACKv46no3

Acknowledgement Atom Indonesia Vol 46 No 3 ack46no3, ack46no3 National Research and Innovation Agency 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1109 10.17146/aij.2020.1109 Atom Indonesia; Vol 46, No 3 (2020): December 2020 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1109/872 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1081 2021-08-30T07:42:43Z aij:ART

Coupled Analysis of Thorium-based Fuels in the High-Performance Light Water Reactor Fuel Assembly Pérez, Y. García, C. R. Mena, F. L. Castro, L. Supercritical water; HPLWR; CFD; Thorium-based fuels; Neutronic/thermal-hydraulic coupled analysis One of the six selected concepts to be part of Generation IV nuclear reactors is the Supercritical Light Water Cooled Reactor. The High-Performance Light Water Reactor (HPLWR) is the European version and it is a very promising design. In recent years, interest in the study of thorium-based fuel cycles has been renewed and its possibilities for current LWRs have been evaluated. The use of thorium-based fuels will be fundamental in the future sustainability of nuclear energy, since in addition to its abundance in nature, thorium has an important group of advantages. In this paper, performance of thorium-based fuels in the typical fuel assembly of the HPLWR reactor is evaluated, using a computational model based on CFD and Monte Carlo codes for the neutronic/thermal-hydraulic coupled analysis. The volumetric power density profiles, coolant temperature profiles, fuel temperature profiles and others are compared with those obtained for standard UO2 fuel. When the thorium-based fuels are used, the obtained infinite multiplication coefficients are smaller than the value obtained when UO2 is used, since the 232Th isotope has a lower contribution to the multiplicative properties of the medium than 238U. As a result, a difference of approximately 12 000 pcm was observed. The results verified that the HPLWR is a thermal reactor with a hard spectrum. There are no notable changes in the neutron spectrum if the mass fraction of thorium is slightly varied.  With coupled analysis, the potential benefits of the utilization of thorium-based fuels were verified. Moreover, a significant temperature decrease by 136 K on the center line of the fuel elements was observed. When the mass fraction of thorium increases in the oxides mixture, the weighted average temperature on the fuel elements decreases. National Research and Innovation Agency Universidad Nacional Autónoma de México, Universidad de la Habana. 2021-08-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1081 10.17146/aij.2021.1081 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 141-150 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1081/985 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1374 2024-12-03T02:00:49Z aij:ART

Assessment of the Level of Radioactivity in the Soil in Urban Areas and Building Materials of Arlit City (Agadez-NIGER) Sidibé, M. O. Manga, A. O. Soumana, S. Adukpo, O. K. Natural radioactivity; Gamma spectrometry; Radium equivalent activity; External and internal risk; Soil and building materials samples; Niger's uranium deposits are located in the north, bordering the southern Sahara. Mining activities led to the creation of the town of Arlit in 1969. Uranium mining and uranate production generate large volumes of radioactive solid and liquid tailings, as well as radioactive gases. Through dispersion and transport, these radioactive discharges become a source of contamination to the environment and food chain. The aim of our work is to assess the additional ambient exposure to radioactivity of surrounding populations as a result of mining activities. We assessed the risk of exposure to radionuclides from the uranium-238 decay chain through soil and certain building materials. The methodology used is based on collection of soil, sand, gravel and mud samples, which are analyzed using gamma spectrometry technique. Nine (9) public sites and five (5) building materials quarries were sampled for the work. The radiological parameters calculated are radium equivalent activity (Raeq), absorbed dose rate (D), internal and external risk indices (Hin and Hex) and gamma index (Iγ). For the whole study area, the calculated Raeq values range from 78.67 Bq/kg to 199.32 Bq/kg. These values are below the guideline value of 370 Bq/kg. In terms of air dose rate, however, the average value found was 0.32 mSv/year for the nine public sites considered. This exceeds the threshold value of 0.29 mSv/year corresponding to the selected exposure scenarios. In addition, in the mud (Quarry 5) and the second gravel quarry (Quarry 4), Iγ values greater than unity were found. A comparison is made with the results of similar studies around the world. Interpretation of the data obtained concludes that there is a risk of radiological overexposure at six (6) sites and two (2) quarries. This work is independent research which sheds new light on the issue of uranium mining activities impact on the environment in Arlit. National Research and Innovation Agency OUSMANE MANGA Adamou SOUMANA Salifou ADUKPO Oscar Kwaku HAROUNA Idé 2024-11-22 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1374 10.55981/aij.2024.1374 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024; 273-280 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1374/1142 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2566 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2567 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2573 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2574 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2575 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2576 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1374/2577 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1215 2022-08-30T22:41:45Z aij:ART

Elemental Mapping for Characterizing of Thorium and Rare Earth Elements (REE) Bearing Minerals Using µXRF Sukadana, I. G. Warmada, I. W. Pratiwi, F. Harijoko, A. Adimedha, T. B. Yogatama, A. W. Thorium; REE; Micro XRF; AMICS; Mamuju Thorium (Th) anomaly was found in Adang Volcanic Complexes, Mamuju Area, West Sulawesi. This element is associated with high-value elements, the rare earth elements (REE). The minerals containing Th and REE were found in veins mineralization with various types of minerals which are very difficult to identify by conventional method. This research aims to understand the distribution and characterization of Th and REE in individual minerals, using Micro X-Ray Fluorescence (µXRF) analysis and completed by Advanced Minerals Identification and Characterization System (AMICS) software. The samples were collected from vein mineralization in Hulu Mamuju Sector. The contents of Th and REE that were analyzed using X-Ray Fluorescence (XRF) completed by Inductively Coupled Plasma Mass Spectrometry (ICP-MS) are 11,550-74,480 ppm and 6,244.15-48,036.87 ppm, respectively. The minerals that contain Th and REE are britholite ((Ce,Ca)5(SiO4)3OH), aeschynite (Ce,Ca,Fe,Th)(Ti,Nb)2 (O,OH)6, cerite (Ce,Ca)9(Mg,Fe)(SiO4)3(HSiO4)4(OH)3, monazite (REE,Th(PO4)), thorite (Th(SiO4)), andthorutite (Th,U,Ca)Ti2(O,OH)6 associated with other minerals such as pyrite, actinolite, apatite, ilmenite, hematite, zircon and ankerite. Some minerals are uncommon minerals and are only characterized by detailed elemental mapping. The variety of minerals shows the condition of mineralization influenced by carbonatite magma and the hydrothermal process of mineralization National Research and Innovation Agency 2022-07-29 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1215 10.17146/aij.2022.1215 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 87-98 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1215/1021 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1215/2097 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1215/2098 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1215/2099 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1215/2153 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1651 2026-02-26T03:01:50Z aij:ART

Optimizing Quality Assurance in Breast IMRT Treatment Plans: A Comparative Study of Point Dose and 2D Dose Verification Herwiningsih, S. Noor, J. A. E. Widodo, C. S. Munthe, D. Y. B. Hentihu, F. K. Breast cancer; Intensity-Modulated Radiation Therapy (IMRT); Dose verification; Quality assurance; Isocenter shift; Radiation therapy Intensity-Modulated Radiation Therapy (IMRT) requires rigorous dose verification to ensure accurate radiation delivery. This study evaluates point dose verification and 2D dose verification techniques in detecting dose discrepancies due to isocenter shifts in IMRT treatment for post-mastectomy breast cancer cases. Five post-mastectomy breast IMRT plans were retrospectively analyzed, with phantom-based measurements compared against Treatment Planning System (TPS) calculations. The results indicate that point dose verification provides reliable absolute dose measurements, but lacks spatial resolution, whereas 2D verification captures dose variations more effectively. Dose discrepancies remained within acceptable limits for shifts up to ±3 mm, but shifts of ±5 mm or more resulted in clinically significant deviations. Gamma Passing Rates (GPR) decreased substantially beyond ±5 mm shifts, underscoring the importance of precise patient positioning. These findings support the integration of both verification methods to improve IMRT quality assurance, particularly in resource-limited settings. Future advancements in AI-driven dosimetry and real-time in vivo monitoring may further optimize dose verification, enhancing treatment accuracy and patient safety. National Research and Innovation Agency 2025-08-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1651 10.55981/aij.2025.1651 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 187-194 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1651/1180 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2772 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2773 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2774 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2775 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2777 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1651/2778 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1261 2023-06-03T02:55:28Z aij:ART

Patient-Specific Pre-Treatment VMAT Plan Verification Using Gamma Passing Rates Arsalan, M. Z. Kakakhel, M. B. Shamshad, M. Afridi, T. A. VMAT, Treatment Planning System Gamma Analysis Octavius 4D Setup Gamma Acceptance Criteria Continuous gantry motion, continuous beam modulation, and variable dose rate are used in volumetric modulated arc therapy (VMAT) to obtain highly conformal radiation therapy dose distributions. Several errors during daily radiation therapy treatment can be sources of uncertainties in dose delivery. These errors include monitor unit calculation errors and other human mistakes. Due to the uncertainties in the excessively modulated VMAT plan, the intended dose distribution is not delivered perfectly, leading to a mismatch between the measured and planned dose distributions. This necessitates an extensive and effective quality assurance (QA) program for both machine and patient. In this study, VMAT QA plan verification of 62 head and neck (HN) and 19 prostate cases was done using Octavius 4D setup with its associating VeriSoft gamma analysis software. The plans showed a maximum 3D gamma passing rate with 4 mm/3 % gamma acceptance criteria, i.e., 99.7 % for the HN cancer cases and 99.5 % for the prostate cancer cases. Local gamma analysis was also performed for both regions. Furthermore, 2D and volumetric gamma analyses were also carried out. Gamma analysis with respect to different axis was also carried out. It was known that the transversal axis showed    the highest gamma passing rate in both HN and prostate cases, i.e., 99.17 % and 98.3 %, respectively. The transverse axis came to be a better fit for the planned dose distribution. National Research and Innovation Agency NA 2023-04-14 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1261 10.55981/aij.2023.1261 Atom Indonesia; VOL 49, NO 1 (2023): APRIL 2023; 53-59 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1261/1065 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1261/2271 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1261/2272 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1261/2273 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1261/2274 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1012 2020-12-16T02:45:17Z aij:ART

Eye Lens Doses Received by Radiation Workers in Interventional Medical Procedures Hiswara, E. Kartikasari, D. Sofyan, H. Nuraeni, N. Sandy, K.Y.P. Medical radiation worker; Eye lens doses; Interventional procedure; Dose limit The International Commission on Radiological Protection (ICRP) has recently recommended that the occupational dose limit for the eye lens be reduced to 20 mSv per year, averaged over defined periods of 5 years, with no single year exceeding  50 mSv. ICRP clearly states that the recommendations are chiefly based on epidemiological evidence that suggested the eye lens dose threshold for cataract induction revised downwards from 2-5 Gy to about 0.5 Gy. Interventional medical workers are at greater health risk from radiation exposure to eyes as a result of the procedures they undertake than most other medical specialists. An extensive study has been carried out to measure the eye lens doses received by 373 interventional medical radiation workers in twelve large hospitals in Indonesia. Measurements were made using Thermo Scientific Harshaw thermoluminescence dosimeter (TLD) chip (size 3.2 mm × 3.2 mm × 0.15 mm) put inside an EYE-D holder placed in the worker’s temple. The procedures performed are grouped based on classification made by the UNSCEAR (United Nations Scientific Committee on the Effects of Atomic Radiation). The results showed that in general the measured data are in an agreement with some published data, even though a large range of doses was observed. The highest mean eye lens dose of 0.2378 mSv per procedure was received by interventionists who worked in the abdominal interventions procedure. Overall, from the results of measurement, it can be concluded that most interventionists might receive eye lens dose exceeding the dose limit if the procedures are carried out on daily basis, and the abdominal interventions procedures were found to be the ones that give the highest risk to the eye lens of workers as it delivered the highest dose to this particular organ. National Research and Innovation Agency National Nuclear Energy Agency (BATAN) 2020-12-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1012 10.17146/aij.2020.1012 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 135-140 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1012/862 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1679 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1680 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1799 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1800 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1901 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1902 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1903 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1012/1904 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1308 2024-04-16T02:13:18Z aij:ART

Neutronic Design Modification of Passive Compact-Molten Salt Reactor Dwijayanto, R. A. P. Harto, A. W. PCMSR; Temperature coefficient of reactivity; Breeding ratio; MCNP Passive compact molten salt reactor (PCMSR) is a design concept of a molten salt reactor (MSR) currently under development in Universitas Gadjah Mada, Indonesia. It is designed as a thermal breeder reactor using thorium fuel cycle. However, our previous study shows that the original PCMSR design was incorrectly modelled, primarily overestimating its thorium breeding capability. To improve PCMSR neutronic design, we modified the core configuration by the addition of radial fuel channel layers previously nonexistent in original PCMSR core design in various configurations. Neutronic parameters of modified PCMSR geometries in the beginning of life (BOL) were simulated using MCNP6.2 radiation transport code with ENDF/B-VII.0 library. All variations of fuel layer addition show improvement in both temperature coefficient of reactivity (TCR) and breeding ratio (BR), with TCR values became more negative and BR values are larger than unity, ensuring proper breeding capability. Configuration Inner Core-Outer Blanket (IC-OB) achieves the largest BR and lowest doubling time (DT), whilst its TCR is an improvement from the original design. Therefore, IC-OB fuel layer configuration can be applied to redesign the original PCMSR and used in various design optimization scenarios. National Research and Innovation Agency 2024-02-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1308 10.55981/aij.2024.1308 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 9-17 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1308/1105 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1308/2221 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1308/2222 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1308/2223 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1308/2224 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1308/2418 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1038 2021-08-30T07:42:43Z aij:ART

Texture Characterization of Duplex Stainless Steel 2205 Using Neutron Diffraction Method Priyanto, T. H. Muslih, R. Insani, A. Bharoto, B. Ramadhani, A. Mugirahardjo, H. Duplex stainless steel (DSS); Neutron diffraction; Texture; Orientation distribution function (ODF) Duplex stainless steel (DSS) is widely used in chemical processes, petrochemical, oil gas industries, and nuclear technology due to its excellent mechanical properties and exceptional generalized and localized corrosion resistance. In this study, the crystal structure, material phases, and texture characterization of DSS were carried out using the neutron diffraction method. The characterization results show that the duplex has two phases: α (ferrite) and g (austenite), each with a lattice parameter 2.8736 Angstrom and 3.6076 Angstrom, respectively. The sample symmetrization method from triclinic to orthorhombic are used to analyze pole figures. The crystallite orientation in the α and g phases have the opposite direction. The α phase has a crystallite orientation towards {110} 001 or Goss orientation, and the g phase, crystal orientation towards {100} 001 or the cube orientation. The orientation distribution function shows that the orientation strength of ferrite is much stronger than austenite. The crystallite orientation (texture) obtained by the orientation distribution function analysis follows the crystal structure analysis. National Research and Innovation Agency Center for Science and Technology of Advanced Materials, National Nuclear Energy Agency (BATAN) 2021-06-28 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1038 10.17146/aij.2020.1038 Atom Indonesia; Vol 47, No 2 (2021): August 2021; 79-84 2356-5322 0126-1568 10.55981/aij.v47i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1038/976 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1718 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1719 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1720 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1721 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1722 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1723 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1724 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1731 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1940 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1941 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1942 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/1943 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/2025 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/2026 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/2027 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1038/2028 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1512 2024-09-10T08:58:51Z aij:PRVv50no2

Preface Atom Indonesia Vol 50 No 2 prfc50no2, prfc50no2 National Research and Innovation Agency 2024-08-01 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1512 10.55981/aij.2024.1512 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1512/1130 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1161 2022-04-12T03:55:44Z aij:ART

Detection of Spoilage in Canned Pasteurized Milk Using the Radiographic Imaging Technique Thuy, D. T. Tien, H. B. Ngoc, H. B. Kim, T. T. Ngoc, T. T. Radiation application; Non-destructive; X-ray imaging After packed into sterilized containers with a closed and rigorous process, pasteurized milk has been ensured for its hygiene and safety factors. However, distortions can occur during storage and transportation, causing the container to open, allowing harmful microorganisms to enter and damage the product. This research proposed a radiographic imaging technique to detect and evaluate the spoilage of canned pasteurized milk. The X-ray images show that the milk cans, which were left open for three days at 300 K, indicated regions with abnormal density with the smallest detectable size from 100 µm or larger. Density heterogeneity would be clearer in the following days and depending on the sample. An algorithm was developed to identify spoilage products automatically with an accuracy of up to 100 % and a speed of 0.0057 s/product. This approach may be suitable for industrial scale to control the quality of dairy products. National Research and Innovation Agency Vietnamese Education and Training 2022-04-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1161 10.17146/aij.2022.1161 Atom Indonesia; Vol 48, No 1 (2022): April 2022; 45-50 2356-5322 0126-1568 10.55981/aij.v48i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1161/1005 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1161/2125 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1161/2126 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1161/2127 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1161/2128 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1412 2025-08-07T00:44:56Z aij:ART

A Multicenter Study of IMRT Dosimetry Audit Testing Using C-shape Phantom Dwinesti, B. Ryangga, D. Dimitri, F. Handika, A. D. Fadli, M. Putranto, A. M. Y. Suharsono, S Pawiro, S. A. IMRT, Dosimetry audit, Gamma analysis, TLD-rod, Film EBT3 Intensity Modulation Radiation Therapy (IMRT) is a complex radiotherapy technique, so independent verification or dosimetry audits must be performed to ensure that accurate dosing is delivered to patients. This study conducted a multicenter audit using a dosimetry audit method developed from the IAEA dosimetry audit for IMRT/VMAT. The phantom in this study is made of acrylic material with two insert structures: planning target volume (PTV) and organ at risk (OAR). Phantom was scanned with a CT simulator at each hospital, and dose distribution was simulated with a PTV prescription dose of 4 Gy/2 fraction (D95 % = 95 %, D2 % < 107 %, and Dmax < 110 %) and a maximum OAR dose of 2.8 Gy. Dose evaluation in this study used TLD-rod for point dose and Gafchromic Film EBT3 for 2D dose distribution. Gamma evaluation was performed for film dose distribution with 3 %/3 mm and 3 %/2 mm criteria. The IMRT dosimetry audit using a C-shape phantom was tested in seven linacs (dynamic and static MLC) from six centers in Jakarta. The TLD results for PTV and OAR point dose show that all 14 IMRT plans meet deviation tolerance within ± 5 %. The film EBT3 evaluation identified that almost all plans pass the minimum 95 % gamma passing rate for 3 %/3 mm criteria and the minimum of 90 % for 3 %/2 mm. Three plans from three centers were also compared to the Gayatri (2022) study data from the same centers. Both results showed that all plans pass the action level ≥ 90 % for both 3 %/2 mm and 3 %/3 mm. Our audit dosimetry study approach employs a small and compact C-shaped phantom and dosimetry, facilitating easier distribution for remote audits. This study could serve as a starting point for remote audits leading to broader multicenter research in Indonesia. National Research and Innovation Agency Universitas Indonesia 2025-07-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1412 10.55981/aij.2025.1412 Atom Indonesia; Vol 51, No 2 (2025): AUGUST 2025; 131-136 2356-5322 0126-1568 10.55981/aij.v51i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1412/1174 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1412/2728 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1412/2729 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1412/2730 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1284 2022-12-23T13:45:34Z aij:ACKv48no3

Acknowledgement Atom Indonesia Vol 48 No 3 ack48no3, ack48no3 National Research and Innovation Agency 2022-11-27 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1284 10.17146/aij.2022.1284 Atom Indonesia; Vol 48, No 3 (2022): December 2022 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1284/1055 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1955 2026-04-06T04:41:12Z aij:CVRv52no1

Cover Atom Indonesia Vol 52 No 1 Indonesia, Atom National Research and Innovation Agency 2026-02-26 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1955 10.55981/aij.2026.1955 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1955/1213 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/979 2020-09-25T01:54:19Z aij:ART

Characteristics of Stable Isotope Compositions (δ18O and δ2H) of Surface Water in Bengkulu City Zega, B.N. He, S. Lubis, A.M. Hydrological processes; Local meteoric water line; Picarro L2140-i; Stable isotopes; Surface water Indonesia as an archipelagic country has a unique location and topography, and the El Niño-Southern Oscillation (ENSO) is observed in this region, resulting in complex weather and climate variability. As a result, Indonesia including Bengkulu experiences regular natural disasters. Stable isotopes (δ18O and δ2H) have been used as natural tracers in solving water resources and water-related problems. The aim of this research is to investigate the variations of stable isotopes in Bengkulu City from three locations, namely Serut and Hitam Rivers and the Universitas Bengkulu (UNIB) lake, and to understand the hydrological processes in Bengkulu City. In this research, samples of surface water from Serut and Hitam Rivers and UNIB Lake in Bengkulu City were collected over five months between December 2018 and April 2019. Stable isotope compositions of these water samples were examined to understand the local hydrological processes. The result shows that the water samples are generally situated at the right side of Local Meteoric Water Line (LMWL) in δ18O and δ2H plot, indicating that water samples are more enriched in 18O and 2H as compared with the rainwater due to fractionation processes. The surface water samples define a local evaporation line with a slope of 6.536 while the LMWL has a slope of 7.848. This result indicates a significant evaporation effect on water bodies. Moreover, the slope of the regression line in all water samples was lower than the LMWL, in order of Serut River (7.696) Hitam River (6.851) UNIB Lake (6.436), indicating that UNIB Lake experienced more significant evaporation than river waters, resulting in enrichment in heavy isotopes. Serut River, one of largest river in Bengkulu City, which also plays an important role in flooding in Bengkulu City, has a regression equation similar to the regression line of rainwater (LMWL). It may be indicated that surface water from Serut River is strongly influenced by rainwater. Consequently, high amount of rainfall can affect the water level of Serut River, and can be associated with flooding. Therefore,   long-term monitoring of stable isotopes is very important in the future to provide the pattern of changes in isotopic variation, particularly during flood and drought events as climate-disaster mitigation effort. National Research and Innovation Agency Department of Physics, Faculty of Mathematics and Natural Sciences, University of Bengkulu, Bengkulu 38122, Indonesia arth of Observatory of Singapore, Nanyang Technological University, Singapore 639798, Singapore 2020-08-19 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/979 10.17146/aij.2020.979 Atom Indonesia; Vol 46, No 2 (2020): August 2020; 85-90 2356-5322 0126-1568 10.55981/aij.v46i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/979/840 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1596 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1698 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1742 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1743 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1753 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1853 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1854 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/979/1855 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1291 2023-12-19T03:11:18Z aij:ART

Analysis of Radiation Exposure Level on Linen and Other Objects in Patient Rooms at Nuclear Medicine Installation Putri, A. Zurma, R. Munir, R. Putri, E. R. Radiation contamination; Radiation exposure; Radiation protection; Surveymeter Analysis of radiation contamination levels has been carried out using an Atomtex surveymeter in the patient rooms after thyroid cancer ablation therapy, in the Nuclear Medicine Installation, Abdoel Wahab Sjahranie Hospital. This study aims to measure the level of radiation exposure based on the rate of radiation exposure and radiation contamination of objects in the patient rooms after ablation therapy, and to find out how long linen can be washed since the first measurement. Data collection was carried out once a week, on the same weekday, for five weeks for objects in the patient rooms by using the surveymeter at a fixed distances from the objects’ surfaces. Radiation contamination measurements for linen items were carried out for 3 d by aiming the surveymeter to container containing linen items from certain distances. Based on this study, the level of radiation exposure obtained is categorized as low because the value range is below 10 μSv/h. The radiation contamination for some objects are categorized as low-level exposure because the value is less than 3.7 Bq/cm2. Other objects tend to be in the moderate-level category because the value is more than 3.7 Bq/cm2 and less than 37 Bq/cm2. The values obtained refer to the standard issued by BATAN. It can be concluded that the patient rooms in the Nuclear Medicine Installation of Abdoel Wahab Sjahranie Hospital are safe. National Research and Innovation Agency 2023-12-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1291 10.55981/aij.2023.1291 Atom Indonesia; VOL 49, NO 3 (2023): DECEMBER 2023; 185-192 2356-5322 0126-1568 10.55981/aij.v49i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1291/1096 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2358 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2359 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2360 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2361 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2362 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1291/2363 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1409 2024-09-10T08:58:51Z aij:ART

Preliminary Study of Micronucleus Frequencies and Responses in Thyroid Cancer Patients After Treatment with 131I Therapy Basri, I. K. H. Lusiyanti, Y. Ramadhani, D. Tetriana, D. Dewi, A. R. Purnami, S. Suvivan, V. A. Gani, M. R. A. Kisnanto, T. Micronuclei; Activity; Dose rate; Thyroid cancer; Follow up; Response Radioiodine has become the most widely used to treat an overactive thyroid (hyperthyroidism) and thyroid cancer worldwide. The present research aimed to study the association between micronuclei (MN) frequencies, and follow-up responses after treating thyroid cancer patients with iodium-131(131I). The detection of the MNs assay was carried out by Giemsa staining from lymphocytes obtained from twenty-four thyroid cancer patients one week after receiving 131I treatment at Dharmais Cancer Center Hospital, Jakarta, Indonesia. Follow-up for clinical and laboratory responses grouped into good (stable) and bad (progressive, refractory, and dropout patients) responses, was observed one and six months after treatment. All patients received radioiodine with an activity dose of 30 - 200 μCi. The mean MN frequency in the good response group was 14.22, and that of bad response patients was 17.22. There was no statistically significant difference in MN frequency (p>0.05) between the two groups of patients after six months of treatment. National Research and Innovation Agency 2024-08-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1409 10.55981/aij.2024.1409 Atom Indonesia; Vol 50, No 2 (2024): AUGUST 2024; 143-149 2356-5322 0126-1568 10.55981/aij.v50i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1409/1121 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1409/2449 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1409/2450 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1409/2451 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1409/2452 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1409/2453 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1204 2021-12-13T13:22:00Z aij:CVRv47no3

Cover Atom Indonesia Vol 47 No 3 cvr47no3, cvr47no3 National Research and Innovation Agency 2021-08-13 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1204 10.17146/aij.2021.1204 Atom Indonesia; Vol 47, No 3 (2021): December 2021 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1204/1000 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1503 2025-04-14T03:30:31Z aij:ART

Preliminary Neutronic Studies on RSG-GAS Fuel Element with 4.8 grU/cc and Burnable Poison Wire for Reactivity Reduction Luthfi, W. Setiadipura, T. Su’ud, Z. RSG-GAS; 4.8 grU/cc; Burnable poison wire; Temperature coefficient of reactivity; SRAC2006; Openmc High-density fuel can increase the operating cycle of a nuclear reactor. The G.A. Siwabessy Multipurpose Reactor (RSG-GAS) is a research reactor owned by Indonesia that currently uses 19.75 % enriched uranium silicide fuel (U3Si2-Al) with a uranium density of 2.965 grU/cc. Previous studies have shown that high-density fuel, 4.8 grU/cc, can be used in the RSG-GAS core to extend the operating cycle. Previous studies related to high-density fuel conversion scenarios included a temporary conversion process to a density of 3.55 grU/cc before being increased to 4.8 grU/cc. However, the previous conversion process requires the addition of control rods to suppress the excess reactivity of the RSG-GAS. The current study focuses on determining the configuration of burnable poison wire for the standard fuel element of RSG-GAS (FE) made of cadmium and hafnium to suppress the reactivity (k-inf) of the 4.8 grU/cc fuel element so it could have an initial reactivity closer to the 2.965 grU/cc fuel. 5 pairs of 0.4 mm diameter Cd-wire coated with 0.1 mm AlMg2 cladding can suppress the reactivity of the fuel assembly, while 7 pairs of 0.8 mm diameter Hf-wire without cladding could suppress reactivity longer. The temperature coefficient of reactivity for the moderator temperature (MTC) and fuel temperature (FTC) also becomes more negative in high-density FE RSG-GAS while the amount of Pu-239 produced increases in high-density fuel element. National Research and Innovation Agency Research Center for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency Magister Program on Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung 2025-03-20 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1503 10.55981/aij.2025.1503 Atom Indonesia; Vol 51, No 1 (2025): APRIL 2025; 71-80 2356-5322 0126-1568 10.55981/aij.v51i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1503/1161 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1503/2658 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1503/2659 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1503/2660 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1503/2661 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1191 2022-12-22T17:40:30Z aij:ART

Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON Islam, A. Rahim, T. A. Mollah, A. S. VERA, Depletion, OpenMC, ONIX, DRAGON This research focuses on the comparative analysis of the PWR fuel assembly based on VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python based burnup code system ONIX (a coupling interface for Monte Carlo code OpenMC), and deterministic DRAGON code. The depletion analysis was performed using OpenMC and ONIX with ENDF/B-VII.1 nuclear data library, and DRAGON with SHEM-361 based DRAGLIB format library (ENDF/B-VII.1). The code-to-code analysis on the evolution of , atom number density, and power distribution as a function of burnup has been performed and the result shows a good agreement with the maximum difference within 200 pcm at EOC. However small discrepancy around 90 pcm has been observed in  calculated by DRAGON compared to OpenMC in the presence of integral fuel burnable absorbers (IFBA). The above-mentioned codes have been validated successfully for the first time against PWR fuel assembly based on VERA depletion benchmark problems. It can be concluded that initial implementation of these codes at the Department of Nuclear Science and Engineering under Military Institute of Science and Technology, Dhaka, was successful and that further research works are to be performed to utilize these codes for depletion/neutronics calculation of existing 3MW TRIGA Mark-II research reactor and VVER-type power reactor that is to be commissioned in Bangladesh. National Research and Innovation Agency 2022-12-06 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1191 10.17146/aij.2022.1191 Atom Indonesia; Vol 48, No 3 (2022): December 2022; 193-203 2356-5322 0126-1568 10.55981/aij.v48i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1191/1048 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1191/2189 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1191/2194 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1191/2195 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1191/2196 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1655 2026-04-09T04:14:14Z aij:ART

Development of Burnup Fraction Calibration Curve for the Silicide Fuel Equilibrium Core of the RSG-GAS Reactor Pinem, S. Sulistyo, F. Y. Liem, P. H. Hakim, A. A. Luthfi, W. burnup; reactivity method; RSG-GAS; Serpent2 code The reactivity value of the RSG-GAS research reactor fuel with different burnup levels has been measured. The primary objective of this study is to establish the burnup calibration curve using the equilibrium core reactivity method of the RSG-GAS reactor. The reactivity value of each fuel element was measured at the same position within the reactor core to ensure that the measured burnup corresponds to the experimental core. The reactivity value of each fuel element was then extrapolated with the known burnup of the fuel element. The total control rod worth measurement was compared with Monte Carlo Serpent2 code calculations. The experimental fuel reactivity results were compared with the calculation results, showing a maximum discrepancy of -4.88%. Based on the reactivity measurement and calculation results, a fuel burnup calibration curve was successfully developed, which can be used to determine the burnup fraction of the RSG-GAS reactor. National Research and Innovation Agency 2026-03-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1655 10.55981/aij.2026.1655 Atom Indonesia; Vol 52, No 1 (2026): APRIL 2026; 15-21 2356-5322 0126-1568 10.55981/aij.v52i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1655/1201 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1655/2894 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1655/2895 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1655/2896 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1655/2897 Copyright (c) 2026 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1325 2023-06-03T02:47:20Z aij:ACKv49no1

oai:ojs.aij.batan.go.id:article/1304 2023-08-29T02:15:31Z aij:ART

External Bremsstrahlung Studies on Films of Lead Monoxide Filled Polycarbonate Composite Kandagal, V. A. Lobo, B. External bremsstrahlung; Effective atomic number; Polycarbonate; Lead monoxide; Composite; Beta particles The development of high-Z (high atomic number) radiation shielding materials is vital in order to protect personnel who work with harmful gamma radiation sources. At the same time, the emission of external bremsstrahlung (EB) radiation in those shielding materials when the radiation source emits beta particles as well as gamma radiation is also of prime concern.The production of EB in films of lead monoxide (PbO) loaded polycarbonate (PC) composite at eleven different filler levels (FLs) varying, in terms of weight fraction, from 0.0 % up to 10.0 % were investigated experimentally by using beta particles from strontium-90/yttrium-90 (90Sr/90Y) radioactive source. A nonlinear relation is observed between EB intensity and target thickness. The effective atomic numbers of the prepared PbO-filled PC composite films (at different FLs) were determined via EB measurements, followed by calculations, and the values obtained were compared with the modified atomic numbers which were determined for the same composite films (at different FLs) using the Markowicz and Van Grieken equation, and it was found that they are in good agreement. Finally, the atomic number dependence of EB in these composite films (PbO-filled PC composites) has been studied. It is obtained that the intensity of EB spectra depends on the square of the atomic number of the target material. National Research and Innovation Agency NIL 2023-08-29 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1304 10.55981/aij.2023.1304 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 137-143 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1304/1086 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1304/2331 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1304/2332 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1304/2333 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1304/2334 Copyright (c) 2023 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1040 2021-06-28T15:53:36Z aij:ART

Investigation on the Background Radiation of Abakaliki Rice Mill in Ebonyi State, Nigeria Nwachukwu, A. Ikeagwuani, F. C. Adeboje, A. O. Radiation monitor; Background radiation; Exposure rates; Permissible limits; Dose rates; Cancer risk This study investigated the background ionizing radiation of Abakaliki rice mills. The requirement to monitor this site is because the prevalent activities in the site suggest that it is a source of ionizing radiation. The activities include fuel stations and excavation sites. Other sources are various chemicals and agrochemicals (like Phosphate, Uranium, Thorium, and Radium) used during the planting of the different rice species. There is, therefore, an urgent need to investigate the radiation level of Abakaliki rice mills in Ebonyi state, Nigeria to ascertain if it has passed the safety standards. The investigation was carried out using the Radalert 100 radiation monitor and a geographical positioning system (Garmin GPSMAP 765). The studied site was split into different points with each representing a mill that houses different grinding plants. This study included all the sections of the mill. The mean background radiation exposure rate ranges from 0.014mRhr-1to 0.0204mRhr-1. The obtained values are higher than the world standard limit of 0.013mRhr-1 recommended by ICRP except point 7 which corresponds to the top of the rice husk dumpsite. The calculated absorbed dose rates for the various sections of the mill ranged from 99.18 nGh-1 to 177.48 nGyh-1. These values of absorbed dose rates were observed to be far higher than the world permissible value of 89 nGyh-1. The annual effective dose equivalent (AEDE) for the exposure values ranged from 0.122 mSvy-1 to 0.218 mSvy-1 which are far lower than the ICRP permissible limits of 1.00 mSvlyr for the public and therefore implies absence of any immediate radiological risk. The excess lifetime cancer risk for the mill users were all above the 0.29 × 10-3 world recommended value. This suggests a possibility of the rice mill workers developing radiation-related illnesses over time. National Research and Innovation Agency AVR Green Albatross Solutions Nig. Ltd, Department of Physics 2021-04-07 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1040 10.17146/aij.2021.1040 Atom Indonesia; Vol 47, No 1 (2021): April 2021; 25-30 2356-5322 0126-1568 10.55981/aij.v47i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1040/890 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/1751 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/1996 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/1997 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/1998 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/1999 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1040/2000 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1115 2021-12-09T05:39:37Z aij:ART

Theoretical Inspecting of 211At Radionuclide via Coupled-Channel Model for Fusion Reaction of Stable Nuclei Cinan, Z. M. Başkan, T. Erol, B. Yılmaz, A. H. Astatine-211; Coupled channel model; Fusion barrier distributions; Fusion cross sections; Heavy-ion fusion reaction; Radionuclide This work has been carried out to obtain and inspect of 211At radionuclide through fusion reaction. Cross-sections for fusion reaction have been calculated with different interaction combinations and excitations for 19F + 192Os and 18O + 193Ir  reactions. All calculations have been performed on NRV Knowledge Base, CCFULL code, and Wong’s Formula. Firstly, we assigned reaction parameter values taking into account the compatibility with the experimental data 19F + 192Os reaction. Afterward, to enrich studies on 211At radionuclide, we proposed 18O + 193Ir reaction which did not have experimental data in the literature with the method and parameter values we determined. We examined the effects of phonon excitations in projectile and target nuclei on fusion cross sections and barrier distributions. With our research, we showed that the coupled channel model and the calculation codes used to explain the fusion cross-section data and barrier distributions well. This research sheds light on the importance of analyzing important medical radionuclides such as 211At by heavy-ion fusion reactions and encourages new researches. National Research and Innovation Agency The authors declare that this paper is unfunded. 2021-11-16 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1115 10.17146/aij.2021.1115 Atom Indonesia; Vol 47, No 3 (2021): December 2021; 163-172 2356-5322 0126-1568 10.55981/aij.v47i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1115/989 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1115/1920 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1115/2056 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1115/2057 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1115/2058 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1115/2075 Copyright (c) 2021 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1574 2024-12-03T02:00:48Z aij:PRVv50no3

Preface Atom Indonesia Vol 50 No 3 Indonesia, Atom National Research and Innovation Agency 2024-09-10 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1574 10.55981/aij.2024.1574 Atom Indonesia; Vol 50, No 3 (2024): DECEMBER 2024 2356-5322 0126-1568 10.55981/aij.v50i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1574/1147 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1174 2022-08-22T00:27:11Z aij:ART

Assessment of Radiological Hazards in Soil, Water and Plants Around Coal Power Plant Murniasih, S. Prabasiwi, D. S. Sukirno, S Radioactivity; Environmental samples; Annual effective dose; Radiation hazard indices; Coal-fired power plants The existence of a Coal-Fired Power Plant (CFPP) is suspected to affect the environment quality, especially the increment of natural radionuclides content which is found in coal as raw material.Therefore, systematic analysis of natural radionuclides (210Pb, 234Th, 238U, 228RA, 40K, 226RA and232Th) in water, soil, and plantwere conducted to establish a database of environmental contamination in the area around a CFPP. This research was conducted in the area around Adipala Cilacap CFPP which operates with two towers. Samples were taken from three locations around the Adipala CFPP based on the secondary wind direction data from Indonesian Agency for Meteorological, Climatological, and Geophysics in the 2018 dry season. Samples were prepared in the Radiochemistry Laboratory, Center for Accelerator Science and Technology, BATAN.The concentration of radioactivity in environmental samples were analyzed using gamma spectrometry with a high purity germanium detector for 24hours after reaching its secular equilibrium. The result of samples analysesshown that the mean value of the radionuclides specific activities (210Pb, 234Th, 238U, 228RA, 40K, 226RA and232Th) for water, cassava leaves, grass, and soil were 0.789 Bq/L, 14.685 Bg/kg, 15.036 Bq/Kg, and 75.083 Bq/kg, respectively. The mean of radium equivalent activity (Raeq)for water, cassava leaves, grass, and soil were 1.692, 30.792, 18.699 and 137.513 Bq/kg, respectively. The absorbed dose rate (ADR)for water, cassava leaves, grass, and soil were0.775, 14.332, 8.627, and 64.135 nGy/h, respectively, whilst the annual effective dose rate (AEDR) were 0.004, 0.070, 0.042, and 0.315 mSv/y. The mean of external and internal hazard indices(Hex and Hin) for water, cassava leaves, grass, and soil were 0.005 and 0.006, 0.083 and 0.129, 0.050 and 0.078, and 0.371 and 0.554, respectively, while the mean of excess lifetime cancer risk (ELCR)wre 0.014×10-6, 0.246×10-6, 0.148×10-6, and 1.101×10-6. According to the calculation of radiation hazard index in this research, it was understood that all parameters of all samples were within acceptable limits by the world average value reported by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). National Research and Innovation Agency Center for Accelerator Science and Technology BATAN 2022-08-18 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1174 10.17146/aij.2022.1174 Atom Indonesia; Vol 48, No 2 (2022): August 2022; 137-145 2356-5322 0126-1568 10.55981/aij.v48i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1174/1027 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1174/2071 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1174/2072 Copyright (c) 2022 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1501 2026-02-26T03:01:50Z aij:ART

Analysis of Alpha and Lithium-7 Particle Energy Deposition in BNCT using Geant4 Simulation Charef, K. Ahlaf, F. Z. Khoulaki, Y. Benchekroun, D. Harrass, H. Fathi, I. Makhkhas, Y. Boron neutron capture therapy; Lithium-7 ion; Alpha particles; Geant4; Monte Carlo; Radiotherapy This study investigates the microdosimetric characteristic of Boron Neutron Capture Therapy (BNCT) using high-fidelity Monte Carlo simulations to quantify the energy deposition distributions of alpha and lithium-7 particles within cellular structures. The Geant4 toolkit is utilized to model various physics lists and water representations, aiming to optimize the accuracy of BNCT simulations. Dosimetric and microdosimetric studies using these Monte Carlo techniques are conducted to examine the behavior of the produced alpha and lithium-7 particles and their energy deposition in different cellular compartments. Our findings contribute to the understanding of BNCT’s effects at the cellular level, which is crucial for advancing treatment planning and minimizing side effects. National Research and Innovation Agency 2025-10-30 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1501 10.55981/aij.2025.1501 Atom Indonesia; Vol 51, No 3 (2025): DECEMBER 2025; 229-241 2356-5322 0126-1568 10.55981/aij.v51i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1501/1189 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1501/2833 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1501/2834 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1501/2835 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1501/2836 Copyright (c) 2025 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1248 2023-08-29T02:15:31Z aij:ART

Synthesis of Polyvinyl Alcohol (PVA)-Gelatin Hydrogel from White Snapper (Lates calcarifer, Bloch) with Gamma Irradiation and Its Characterizations Hariyanti, H Erizal, E Apriyani, R. Z. Perkasa, D. P. Lestari, I. Rahmi, H. Polyvinyl alcohol (PVA); Gelatin; Gamma irradiation; Hydrogel; Wound dressing The application of nuclear technology in the health sector is increasing. One example is the use of irradiation in production of wound dressings. Research activities have been conducted to study whether polyvinyl alcohol (PVA)-gelatin-based hydrogel from white snapper scales can be processed using gamma irradiation into wound dressings. A series of PVA (10 %) solutions containing gelatin in various concentrations (0-4 %) were treated with three freeze-thaw cycles and then irradiated at doses of 10 and 20 kGy. They were subsequently characterized using Fourier transform infrared (FTIR) spectroscopy and scanning electron microscope (SEM). Gel fraction, water absorption, and percentage of hydrogel water evaporation rate were tested gravimetrically, while the elongation at break and the tensile strength of the hydrogels were tested with a universal testing meter. The evaluation showed that the hydrogel gel fraction decreased with increasing gelatin concentration from 0 % to 4 % for both irradiation doses (10 and 20 kGy). The rising gelatin concentration demonstrated that increasing gamma radiation dose improved the hydrogel's water absorption, evaporation rate, tensile strength, and elongation at break. PVA-gelatin hydrogel with irregular pore structure was observed from SEM test results. The FTIR measurement results confirmed the formation of crosslinks in the hydrogel matrix. The PVA-gelatin hydrogel produced through gamma irradiation could be used for wound dressings. National Research and Innovation Agency 2023-05-08 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1248 10.55981/aij.2023.1248 Atom Indonesia; VOL 49, NO 2 (2023): AUGUST 2023; 69-75 2356-5322 0126-1568 10.55981/aij.v1i2 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1248/1074 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1248/2285 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1248/2286 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1248/2287 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1248/2288 http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/902 2020-12-16T02:45:17Z aij:ART

Finite-Difference Time-Domain Simulations of Radon Transport in Porous Media Tayebi, A. Bezzout, H. El Maghraoui, M. Faylali, H. El Radon; Radon transport equation; Finite-difference time domain (FDTD); Diffusion coefficient In this work, an efficient algorithm, using a finite-difference time-domain (FDTD) technique, is proposed for modeling the variation of radon concentration as a function of soil structure parameters and vice versa. The development of the FDTD model is based on the simultaneous resolution of the radon transport equation in a porous, homogeneous medium, namely the soil. This equation describes the concentration of radon per pore volume unit. The numerical results are compared with those of the literature or with the theoretical ones. National Research and Innovation Agency Ibn Tofail Université, Département of physics 2020-12-15 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/902 10.17146/aij.2020.902 Atom Indonesia; Vol 46, No 3 (2020): December 2020; 171-175 2356-5322 0126-1568 10.55981/aij.v46i3 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/902/864 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1266 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1274 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1275 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1898 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1899 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/902/1900 Copyright (c) 2020 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0

oai:ojs.aij.batan.go.id:article/1329 2024-04-16T02:59:54Z aij:ART

Radiological Risk to Inhalation of Thoron Gas from Medical Materials Samples Derived from Medical Plants in Iraq Abojassim, A. A. Lawi, D. J. Hassan, A. B. Pollution by thoron is one of the factors that is harmful to human health. Medical materials, especially those derived from plants, have natural ingredients which are a major source of natural radioactivity, thoron being one of them. Therefore, the presence of harmful radioactivity in these materials is a matter of concern. This study determined the concentrations of thoron (220Rn or radon-220) from 70 samples of medical materials derived from medical plants using a CR-39 detector. Samples are drugs (solid), skin creams, herbs, toothpaste, drugs (liquid), and cosmetic products found in Iraqi pharmacies. Also, radiological risks such as Annual Effective Dose (AED), Excessive Lifetime Cancer Risk (ELCR), and Lung Cancer Case (LCC) due to inhalation of thoron from medical materials samples in pharmacies were calculated. The results show that the results of the thoron  concentrations in the samples of medical materials ranged from 1.02 Bq/m3 to 74.53 Bq/m3, with an average value of 18.21 ± 2.00 Bq/m3. The range values of AED, ELCR (×10-3) and LCC (×10-6) were 0.01-0.588 mSv/y, 0.04-2.36, and 0.18-10.58, respectively. It was als found that the thoron concentrations in samples of the present study vary from a minimum of 12.82 Bq/m3 in cosmetic products samples to a maximum of 30.29 Bq/m3 in herbs samples. Nonetheless, all thoron and radiological risk values were lower than the acceptable world limit (thoron = 200-300 Bq/m3  by ICRP and AED = 1.1-4.4 mSv/y by UNSCEAR). National Research and Innovation Agency Thoron concentrations Radiological Risk Medical materials CR-39 detector Iraqi Pharmacies 2024-04-02 info:eu-repo/semantics/article info:eu-repo/semantics/publishedVersion application/pdf https://atomindonesia.brin.go.id/index.php/aij/article/view/1329 10.55981/aij.2024.1329 Atom Indonesia; VOL 50, NO 1 (2024): APRIL 2024; 49-54 2356-5322 0126-1568 10.55981/aij.v1i1 eng https://atomindonesia.brin.go.id/index.php/aij/article/view/1329/1111 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2425 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2426 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2427 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2428 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2429 https://atomindonesia.brin.go.id/index.php/aij/article/downloadSuppFile/1329/2430 Copyright (c) 2024 Atom Indonesia http://creativecommons.org/licenses/by-nc-sa/4.0