001^ID2500001
008^S07/01/I/M/U
009^M
100^Meliana, Alfitri
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^A comparative study of the security of land transport of nuclear and radioactive materials in Indonesia and the Japan Atomic Energy Agency
230^Studi komparatif keamanan transportasi darat bahan nuklir dan bahan radioaktif di Indonesia dan Japan Atomic Energy Agency
300^INIS-ID--0060
403^2023
500^177 p.
600^(IN)
610^44 refs.; 10 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SECURITY; LAND TRANSPORT; RADIOACTIVE MATERIALS; INDONESIA; SABOTAGE; TRANSPORT REGULATIONS; TRANSPORTATION SYSTEMS
009^X/EN
860^The increasing use of nuclear and radioactive materials in Indonesia necessitates the transportation of nuclear and radioactive materials for their distribution to end users. Transporting nuclear and radioactive materials requires stringent security measures to prevent theft and sabotage in order to ensure their safety, among others is the availability of regulations. Regulatory literature in Indonesia and Japan, as well as IAEA NSS No. 9-G (Rev. 1) and IAEA NSS No. 26-G, were reviewed as part of qualitative research. In order to conduct a comparative analysis of the safety system of nuclear material transportation in Indonesia and JAEA, interviews and field observations were conducted. A scale that has been validated by nuclear security experts in Indonesia is utilized for comparative analysis. The results of the analysis indicate that Indonesia's nuclear transportation security management system differs from that of the JAEA in terms of rules and practices, particularly in the areas of regulation for security in nuclear material and radioactive material in transport, training and transportation security awareness, but remains in compliance with IAEA guidelines. This study provides recommendations for enhancing the security system for the transportation of nuclear and radioactive materials in Indonesia in the areas of regulation and training. (author)
001^ID2500002
008^S36/01/I/M/U
009^M
100^Gracia, Angel Natalia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The influence of variation in synthesis methods of zirconium hydroxyapatite nanoparticles on their photodynamic response
230^Pengaruh variasi metode sintesis nanopartikel hidroksiapatit zirkonium terhadap respon fotodinamiknya
300^INIS-ID--0061
403^2023
500^53 p.
600^(IN)
610^46 refs.; 18 figs.; 9 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; ZIRCONIUM; NANOPARTICLES; THERAPY; NEOPLASMS; ADVANCED LIGHT SOURCE; RADIATIONS; SENSITIVITY; METALS
009^X/EN
860^One of the treatment options that can be done is using PDT (Photodynamic Therapy). Although PDT is a very promising cancer treatment modality, its limited penetration capability becomes a barrier in treating cancers located deep inside the body. Therefore, the commonly used light source in PDT is replaced with X-rays. In PDTX, to enhance radiation sensitivity for generating Reactive Oxygen Species (ROS), high atomic number metal materials are used as radiosensitizers. In this research, zirconium is used as the metal material for radiosensitizer. In this study, the drug carrier agent used is Hydroxyapatite nanoparticles (HAp). However, these Hydroxyapatite nanoparticles tend to be unstable due to agglomeration in water-based solvents. To minimize agglomeration in HApZr nanoparticles, silica is added as a template in this research to produce smaller-sized HApZr. The measurement results show that the hydrodynamic diameter of the synthesized HApZr particles with silica template ranges from 339 to 6000 nm and in the emulsion method ranges from 389 to 6000 nm with a polydisperse particle size distribution. TEM characterization of HApZr particles with silica template shows a nano-crystal needle-like structure with an average length of 31.28 nm obtained from ImageJ software. The XRD data simulation analysis results show a hexagonal crystal form. The solubility test found that the product dissolves the most at pH 4. The Zr content in the product is approximately 16 %. The qualitative determination of ROS shows that HApZr with silica template has a higher ROS content compared to the emulsion method and bio-HApZr. (author)
001^ID2500003
008^S37/01/I/M/U
009^M
100^Lapondu, Ariel Kevin
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Demulsifier DM-1 performance evaluation on oil field X oil quality PT. Pertamina Hulu Rokan
230^Evaluasi kinerja demulsifier DM-1 terhadap kualitas minyak lapangan X PT. Pertamina Hulu Rokan
300^INIS-ID--0062
403^2023
500^34 p.
600^(IN)
610^42 refs.; 9 figs.; 3 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DEMULSIFIERS; PERFORMANCE; OILS; WATER; PETROLEUM; EMULSIONS; DEMULSIFICATION; TEMPERATURE CONTROL; SEPARATION PROCESSES; CONCENTRATION RATIO
009^X/EN
860^Production of oil usually has a high water content. The presence of water in crude oil will cause an emulsion to form. The high level of emulsion that is formed causes a decrease in the quality of the oil that will be sold, so that the selling value of oil decreases compared to oil that has a low level of emulsion. The emulsion problem can be overcome by demulsification using a demulsifier. In this study, the performance of DM-1 demulsifier on oil quality was evaluated. The demulsifier was evaluated with temperature variations of 120 #Degree Sign#F and 160 #Degree Sign#F and concentration variations of 90 ppm, 110 ppm, 130 ppm, 150 ppm, and 170 ppm. The demulsifier performance was tested by bottle test followed by top cut BS&W test to determine the oil quality. The bottle test results showed that the % water-oil separation increased with the influence of temperature and concentration. The results of the %BS&W test showed that the oil quality improved as the demulsifier performance increased. The best temperature and concentration for this demulsifier performance evaluation were 160 #Degree Sign#F and 90 ppm. (author)
001^ID2500004
008^S54/01/I/M/U
009^M
100^Amanda, Citha Kurnia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Study method of passive sampling for radio iodine (1-131) with impregnants and activated charcoal types comparison in Bandung Nuclear Area (KNB)
230^Studi metode passive sampling untuk radio iodine (I-131) dengan penambahan zat aditif dan perbandingan jenis material pada arang aktif di Kawasan Nuklir Bandung (KNB)
300^INIS-ID--0063
403^2023
500^55 p.
600^(IN)
610^49 refs.; 16 figs.; 13 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^IODINE; IODINE 131; CHARCOAL; TRIGA-2-BANDUNG REACTOR; INDONESIA; SAFETY; PERSONNEL; ENVIRONMENT; RISK ASSESSMENT; RADIOACTIVE MATERIALS; MONITORING
009^X/EN
860^Advances in science and technology encourage increased use of nuclear in various fields. However, in addition to the contributions made, the use of nuclear technology must also be carried out with due regard to safety factors for workers, society, and the environment. The use of nuclear technology has the risk of causing negative impacts, namely the release of radioactive materials into the environment, especially the radioisotope iodine-131 (I-131), which can easily enter the body because it is highly radioactive and volatile. Monitoring of releases to the environment and monitoring of radioactivity levels in the environment must be carried out routinely to prevent contamination to the public sphere, one of which is the passive sampling method which is inexpensive, can be carried around, is easier to use, and can be stored for a long time. The passive sampler principle refers to air displacement through a diffusion process. Passive samplers are made using relatively simple materials by utilizing the Internal Quick Filter (Holder) as a protective part of the active charcoal adsorbent. In this study, passive sampling was carried out by varying the adsorbents of ordinary activated charcoal and standard activated charcoal and adding the additives Potassium Iodide (KI) and Sodium Hydroxide (NaOH), with variations in concentration, in 1 M and 5 M and added volume in 5 ml, 15 ml, and 25 ml. Sample storage was carried out in the RISB laboratory with variations of 2 days, 4 days, 6 days and 8 days. It is hoped that the results of passive sampling can be effective in trapping I-131 released in the air. The passive sampling results obtained will be enumerated using a gamma spectrometer (Multichannel Analyzer) and compared the results with the active sampling results. The analysis shows that compared to passive sampling with activated charcoal in market, which the pores has small surface area, the adsorption effectiveness of active sampling is better, activated charcoal in market added with additives can enhance the adsorption's effectiveness compared to standard activated charcoal had been added with TEDA. Additives can enhance the I-131 adsorption's effectiveness, stabilized in 1 M concentration and 5 ml added volume on varied time. The longer the storage time, more I-131 can be adsorbed. (author)
001^ID2500005
008^S37/01/I/M/U
009^M
100^Khoirunnisa, Dina
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Modification of natural zeolite activated with HCl using gamma irradiation and effect on Cu"2"+ waste adsorption
230^Modifikasi zeolit alam teraktivasi HCl dengan iradiasi gama dan pengaruhnya terhadap penjerapan limbah Cu"2"+
300^INIS-ID--0064
403^2023
500^49 p.
600^(IN)
610^23 refs.; 14 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^ZEOLITES; GAMMA RADIATION; IRRADIATION; WASTES; ADSORPTION; ADSORPTION ISOTHERMS; THERMODYNAMICS; COPPER; SURFACE AREA; SPECTROPHOTOMETRY
009^X/EN
860^The study was conducted to determine the effect of irradiation on the surface area of natural zeolite, the isotherm adsorption model, and the thermodynamics of Cu"2"+ waste adsorption process. The research was carried out with initial treatments including washing, activation of zeolite using a 0.05 M HCl solution, followed by irradiation with varying doses of 200, 250, 300, 350, and 400 kGy. Irradiation was performed under wet and dry conditions. The pre-treated zeolite was used to adsorb Cu"2"+ with an initial concentration of 400 ppm to obtain equilibrium time and a relatively good initial treatment based on its surface area determined using the iodine number. The zeolite with the largest surface area was used to determine the isotherm adsorption and thermodynamics of Cu"2"+ adsorption. Isotherm adsorption and thermodynamics experiments were conducted with variations in initial Cu"2"+ concentration and temperature. The equilibrium concentration of Cu"2"+ was determined using UV-Vis spectrophotometry analysis with Na-dithiocarbamate complexation. The equilibrium concentration data and the amount of Cu"2"+ adsorbed per gram of zeolite were evaluated and fitted with Langmuir and Freundlich adsorption models, while temperature variation data were used to determine the thermodynamics of adsorption. To understand the effect of modification, morphological characterization was performed using SEM-EDX. The research results showed that gamma irradiation influenced the particle size of zeolite, thereby affecting its surface area. Based on the research findings, the best treatment was observed with wet irradiation at a dose of 350 kGy, resulting in a surface area of 252.36 m"2/g, or an 8-fold increase compared to natural zeolite (31.54 m"2/g). The adsorption process followed the Freundlich isotherm adsorption model, with an R"2 value approaching 1 (0.9119), and an adsorption capacity of 0.1422 mg/ml. The thermodynamic study of adsorption yielded an enthalpy value of -68.70 kJ/mol, indicating an exothermic process occurring through physisorption. (author)
001^ID2500006
008^S37/01/I/M/U
009^M
100^Ayun, Farah Qurrota
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Activated and gamma-irradiated natural zeolite as an adsorbent for metal ion Cr(VI)
230^Aktivasi dan iradiasi gamma pada zeolit alam sebagai adsorben untuk adsorpsi ion logam Cr (VI)
300^INIS-ID--0065
403^2023
500^80 p.
600^(IN)
610^25 refs.; 18 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^GAMMA RADIATION; ZEOLITES; ADSORBENTS; METALS; CHROMIUM; IRRADIATION; CHEMICAL COMPOSITION; SURFACE AREA; IODINE NUMBER; THERMODYNAMICS
009^X/EN
860^This study is intended to find the effect on zeolite pre-treatment as an adsorbent for Cr(VI). Activated zeolite will be made through physical and chemical activation by NaOH 1 M. Activated zeolite will get irradiation treatment by gamma rays with variation of 0, 100, 200, 300, 400 and 500 kGy doses. Characterization of adsorbent zeolite will be obtained by iodine number and the changes of chemical composition and structure used XRF, XRD, SEM, FTIR and Surface Area Specific using iodine number. This research will study the isotherm and thermodynamics adsorption of Cr(VI) using activated and irradiated zeolite by batch systems. The highest Surface area specific is obtained by activated zeolite with gamma irradiated dose of 300 kGy which is 329,439 m"2/g. The adsorption process of Cr(VI) using activated and gamma-irradiated zeolite at dose of 300 kGy with three different temperatures showed that the adsorption followed the Langmuir isotherm with a maximum capacity of 12,183 mg/g. The The process exhibited an exothermic process, with enthalpy and entropy values of -13,994 kJ/mol dan -0,070432 kJ/mol, respectively. (author)
001^ID2500007
008^S12/01/I/M/U
009^M
100^Maulana, Faris Adam
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effectiveness of using amberlite IRA 402 CL resin to absorb scandium-46 in liquid radioactive waste at PRTRRB
230^Efektivitas penggunaan resin amberlite IRA 402 CL untuk menyerap skandium-46 pada limbah radioaktif cair di PRTRRB
300^INIS-ID--0066
403^2023
500^75 p.
600^(IN)
610^41 refs.; 19 figs.; 10 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^ORGANIC ION EXCHANGERS; RESINS; SCANDIUM 46; RADIOACTIVE WASTES; LIQUID WASTES; INDONESIA; RADIOACTIVE MATERIALS; CONTAMINATION; ION EXCHANGE; GAMMA SPECTROMETERS
009^X/EN
860^Bandung Nuclear Area (KNB) is an area owned by the National Research and Innovation Agency (BRIN) that conducts research and research by utilising radioactive material, namely Sc-46. The benefits brought by the use of Sc-46 can be followed by negative impacts if not paid attention to. The negative impact that can be given is the potential for contamination if there is a release of Sc-46 in water because of its highly radioactive nature and has the potential to contaminate living things around it. In this study, a decrease in activity and reduction of Sc-46 liquid radioactive waste will be carried out using Amberlite IRA 402 CL Resin with the ion exchange method so that it is easier to handle. The ion exchange method is a method consisting of mobile and stationary phases. The ion exchanger used in this study is anion exchange resin. Ion exchange is a method that has many advantages such as low energy used, fast reaction and easy operation process and the materials and reagents used are cheap. In this study, the heating variation of Amberlite IRA 402 CL Resin was carried out with temperatures of 60 #Degree Sign#C, 70 #Degree Sign#C, 80 #Degree Sign#C, 90 #Degree Sign#C, and 100 #Degree Sign#C which were also varied with the ratio between the mass of resin and the mass of waste with a ratio of 1:3, 1:4, 1:5, 1:6, and 1:7 as well as variations with contact times of 30 minutes, 45 minutes, 60 minutes, 75 minutes, and 90 minutes. It is expected that the results of the ion exchanger can be effective in capturing the amount of Sc-46 released in water. The ion exchange results obtained will be enumerated using a gamma spectrometer (multi-channel analyser) and compared the results in order to determine the variation that has the optimum results. The results of the analysis show that the effectiveness of the ion exchange method with a variation of 1:3 ratio has the highest effectiveness, at a variation of 90 minutes contact time is the time with the highest effectiveness, for the variation of resin heating at 80 #Degree Sign#C is the temperature with the highest effectiveness. (author)
001^ID2500008
008^S12/01/I/M/U
009^M
100^Nurfadya, Izma Arlingga
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effect of sulfate ions on the adsorption of uranil carbonate with anion exchange resins
230^Pengaruh ion sulfat terhadap adsorpsi uranil karbonat dengan resin penukar anion
300^INIS-ID--0067
403^2023
500^87 p.
600^(IN)
610^64 refs.; 15 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SULFATES; IONS; ADSORPTION; CARBONATES; ANIONS; RESINS; LIQUID WASTES; URANIUM; NUCLEAR FUELS; MOLYBDENUM 99
009^X/EN
860^Liquid waste containing uranium can be generated from research activities, nuclear fuel fabrication, "9"9Mo radioisotope production, and rare earth elements extraction. Uranium is a very toxic and weak radioactive heavy metal which poses high risks for human and environment. Therefore, the waste containing this element shall be manage in a safe and secure manner to ensure safety. In this study, removal of aqueous uranium is carried by adsorption using anion exchange resin. This method have some advantages, such as effective technique with the features of being cost effective, versatile, and easy to operate for removing trace levels of ions. The purpose of this study is to determine the effect of sulfate ion on the adsorption of uranyl carbonate complexes onto Amberlite IRA402 anion exchange resin. The experiments were carried out by contacting solution containing uranium with the resin in various contact time, pH, and sulfate concentrations. Afterwards, the concentration of aqueous uranium after adsorption experiment was determined using ICP-OES and compared to that of initial solution. On the other hand, the resin was characterized using FTIR, SEM, and XRF. The results show that the adsorption uranium from carbonate and sulfate mixture solution followed pseudo-second-order. The adsorption of uranium from solution with 0.01 M Na_2SO_4 and Na_2CO_3, respectively, was 87 %. The value decreased as the concentration of Na_2SO_4 increased, to 51 % at 0.5 M Na_2SO_4. The maximum adsorption capacity from Na_2CO_3 dan Na_2SO_4 solution, of each concentration was 0.1 M, pH 10 and temperature of 25 #Degree Sign#C was 105.26 mg/g. The values of log selectivity coefficient of the resin for UO_2(CO_3)_3"4"- dan SO_4"2"- ions were 1.27 #+-# 0.35 and -3.06 #+-# 0.22, respectively. The results from this study is necessary to design liquid uranium waste treatment using ion exchange method. (author)
001^ID2500009
008^S12/01/I/M/U
009^M
100^Sari, Junita
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Chrome recycling from simulated batik fixation process waste by gamma irradiation method into potassium dichromate
230^Daur ulang krom dari limbah simulasi proses fiksasi batik dengan metode iradiasi gamma menjadi kalium dikromat
300^INIS-ID--0068
403^2023
500^68 p.
600^(IN)
610^41 refs.; 34 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^CHROMIUM; REPROCESSING; SIMULATION; SOLIDIFICATION; WASTE PROCESSING; GAMMA RADIATION; IRRADIATION; HEAVY METALS; POTASSIUM; CHROMATES
009^X/EN
860^One of the batik-making processes that results in the heavy metal Cr(VI) is the fixation process in the production of batik from natural dyes using a mordant in the form of potassium dichromate (K_2Cr_2O_7). The purpose of this research is to reduce and precipitate Cr in batik fixation waste using gamma irradiation. This technique is employed due to the absence of secondary contamination from the waste and the lack of need for reagents to separate the precipitate. Furthermore, recycling of the Cr precipitate is also conducted to recover Potassium dichromate (K_2Cr_2O_7) using the binary submolten salt method to form potassium chromate (K_2CrO_4), followed by acid addition (acidification). This method is chosen for its energy efficiency and environmental friendliness. Gamma irradiation will generate active species like hydrated electrons (e"-_a_q) and hydrogen atoms (#Bullet#H), which will reduce Cr"6"+ ions to Cr"3"+ and precipitate as Cr(OH)_3 when reacting with hydroxide ions (OH"-). Cr(OH)_3 will undergo calcination at 500 #Degree Sign#C for 5 hours to form Cr_2O_3, which is the main raw material for potassium dichromate production. The optimal precipitation conditions occur at an irradiation dose of 40 kGy, scavenger concentration of 4 M, and pH 9 with a Cr recovery radiation efficiency of 72.57 %. The Cr_2O_3 formation calcination efficiency is 96.93%, the synthesis efficiency into K_2Cr_2O_7 is 59,68 %, and the total Cr recovery is 60.92 %. FTIR results show the formed spectra are Cr(OH)_3, Cr_2O_3, and K_2Cr_2O_7. Based on SEM results, it is observed that the surface of Cr(OH)_3 is rougher than Cr_2O_3, and the surface of K_2Cr_2O_7 is granular with cluster-shaped particles. The obtained Cr(OH)_3 and Cr_2O_3 do not contain impurities, while the obtained K_2Cr_2O_7 contains carbon (C) and nitrogen (N) impurities. (author)
001^ID2500010
008^S12/01/I/M/U
009^M
100^Indriana, Kesi
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Reduction of uranium concentration in liquid waste from yellowcake conversion process by precipitation method
230^Penurunan konsentrasi uranium dalam limbah cair dari proses konversi yellowcake dengan metode pengendapan
300^INIS-ID--0069
403^2023
500^97 p.
600^(IN)
610^30 refs.; 30 figs.; 15 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^REDUCTION; URANIUM; CONCENTRATION RATIO; LIQUID WASTES; URANIUM OXIDES U3O8; PRECIPITATION; PHOSPHATES; SALTS; REAGENTS; DECONTAMINATION
009^X/EN
860^The Pilot Conversion Plant (PCP) facility was designed to convert and refine yellowcake powder (U_3O_8) with a design production capacity of 100 kg of nuclear grade UO_2. Each batch process was expected to generate liquid waste containing uranium. Liquid waste containing uranium still requires further treatment before being discarded. The objective of this research is to recover uranium by precipitation. The precipitation method is widely used because it is relatively cheaper and simpler. The reagents that are used are basic reagents (NaOH, KOH, NH_4OH) and phosphate salt reagents (NaH_2PO_4, KH_2PO_4). Uranium precipitation using basic reagents was varied from pH 3 to 8, while uranium precipitation using phosphate salt reagents was varied with concentrations of 0.01 and 0.1 M (1, 5, 10 mL). Uranium precipitation reaction rate with NaH_2PO_4 and KH_2PO_4 reagents was also studied. The concentration of uranium in the wastewater prior to and post precipitation was analyzed using ICP-OES, and the precipitates were characterized by SEM and XRF. The results of the precipitate analysis by SEM and XRF revealed the presence of uranium elements in the obtained precipitate. The results of the supernatant analysis showed a decrease in uranium concentration after precipitation. The efficiency (%) of uranium concentration reduction with basic reagents (NaOH, KOH, NH_4OH) reached >99 %, while phosphate reagents (KH_2PO_4 and NaH_2PO_4) reached >95 %. The optimal condition of precipitation occurred in UBWC waste using KOH reagent at pH 8, efficiency 99.98 %, and decontamination factor 4.963. (author)
001^ID2500011
008^S12/01/I/M/U
009^M
100^Amalina, Lili Tazkia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Batik wastewater treatment with pseudomonas aeruginosa and electron beam irradiation
230^Pengolahan limbah cair batik dengan mikroorganisme pseudomonas aeruginosa dan iradiasi berkas elektron
300^INIS-ID--0070
403^2023
500^70 p.
600^(IN)
610^50 refs.; 22 figs.; 10 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^WASTE WATER; PSEUDOMONAS; ELECTRON BEAMS; IRRADIATION; INDONESIA; POLLUTION; LIQUID WASTES; PH VALUE; WET OXIDATION PROCESSES; REGULATIONS
009^X/EN
860^Batik is one of Indonesia's cultural heritages that was recognized by UNESCO in 2009. Batik Craft produces industrial wastewater that has the potential to pollute the environment. Batik liquid wastewater has the characteristics of a cloudy and colorful color, high acidity (pH), BOD, COD, and TSS. A relatively new and promising wastewater treatment method is the advanced oxidation processes (AOPs) which were developed and used to treat wastewater contaminated with dyes. Previous research has not succeeded in reducing COD by applicable government regulations based on Central Java Regional Regulation Number 5 of 2012. In this study, batik waste treatment was carried out by biological process using Pseudomonas aeruginosa microorganism and continued with electron beam irradiation, so that it is expected to reduce the content of pollutants. This study used simulated waste made from a Remazol color mixture. The simulated waste from the biological process is then irradiated and tested for wastewater parameters including BOD, COD, pH, TSS, and toxicity. Kinetics studies will also be conducted based on the reduction of color intensity by Pseudomonas aeruginosa bacteria. The results showed that the biological process can degrade the dyes contained in wastewater. From the result of the decrease in absorbance, it is obtained that the degradation of wastewater follows the 2"n"d order with the k value at the peak of the 512 nm wave of 0.8261 L.g"-"1day"-"1. There are three variations of irradiated samples, namely liquid waste with the addition of H_2O_2 and HCl (sample A), liquid waste with bacteria and the addition of H2O2 and HCl (sample B), and liquid waste with bacteria with sample addition of chemicals (sample C). In sample A, post-irradiation with a dose of 80 kGy, has a color degradation percentage of 100 %, BOD 45 mg/L, COD 139.37 mg/L, TSS 11 mg/L, and pH values 2.77. In sample B, post-irradiation with a dose of 80 kGy, has a color degradation percentage of 91.302 %, BOD 258 mg/L, COD 797.55 mg/L, TSS 31 mg/L, and pH values 6.10. In sample C, post-irradiation of 80 kGy has a color degradation percentage of 91.859 %, BOD 758 mg/L, COD 1402.10 mg/L, TSS 23 mg/L, and pH values 6.40. BOD and COD values from the results of this study are still not in accordance with the applicable quality standards of 60 mg/L for BOD, and 150 mg/L for COD. Toxicity testing showed that samples A and B had a Very High Acute Toxicity category while sample C at irradiation doses of 30, 40, 50, and 80 kGy had a High Acute Toxicity category. (author)
001^ID2500012
008^S61/01/I/M/U
009^M
100^Dewanti, Maria Rosa
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Cetuximab modified zirconium hydroxyapatite for EGFR targeting photodynamic and radioimmunotherapy therapy of lung cancer
230^Nanopartikel hidroksiapatit zirkonium termodifikasi cetuximab untuk terapi fotodinamik dan radioimunoterapi kanker paru spesifik target EGFR
300^INIS-ID--0071
403^2023
500^73 p.
600^(IN)
610^79 refs.; 39 figs.; 16 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^ZIRCONIUM; RADIOIMMUNOTHERAPY; THERAPY; LUNGS; NEOPLASMS; GAMMA RADIATION; TUMOR CELLS; METALS; PHOTOSENSITIVITY; DRUGS
009^X/EN
860^Photodynamic therapy has good prospects in lung cancer therapy because of minimal invasion, unfortunately this is limited by its poor penetration ability. To overcome this, the light source in PDT can be replaced with X-rays (PDTX) to generate Reactive Oxygen Species (ROS) which have the potential to destroy cancer cells. In PDTX, to produce ROS, metal materials can be used as radiation sensitive substances or called photosensitizers. This research will use Zr as a radiation sensitive substance. In this study, the drug delivery agent used was hydroxyapatite (HAp) nanoparticles. The specificity of drug delivery will be increased by using active targeting through HAp surface modification with cetuximab. To add to the therapeutic modality, the HApZr compound will be labeled using the negative beta emitting isotope 177Lu as the radioisotope used in radioimmunotherapy. The optimum ratio between antibody and nanoparticles that can bind is 50 #Greek Small Letter Mu#g of antibody in 200 mg of nanoparticles. Cellular ROS formed increased in [177Lu]Lu-HApZr-cetuximab, the addition of 7.81 ng/mL began to be effective to increase cellular ROS with the highest intensity at 125 ng/mL. The radiolabeling with the best results was obtained using carrier-free 177Lu with a yield of 98.68 % and 98.85 % The highest cellular uptake was at 30 minutes with a yield of 50 %. The product characterization results with EDX obtained stoichiometry (Ca + Zr)/P = 1.7021 on the results of the XRD data simulation analysis showing a hexagonal crystal shape. The solubility test obtained the most soluble products at pH 4. The amount of Zr in the product was calculated as much as 17.94 %, the hydrodynamic diameter as measured by PSA was 126 nm. (author)
001^ID2500013
008^S37/01/I/M/U
009^M
100^Aisy, Mayang Khoirunnisa Rihaadatul
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis of lithium battery cathode precursor NMC 811 with the addition of lanthanum dopant
230^Sintesis prekursor katoda baterai litium NMC 811 dengan penambahan dopan lantanum
300^INIS-ID--0072
403^2023
500^55 p.
600^(IN)
610^62 refs.; 29 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; LITHIUM; ELECTRIC BATTERIES; CATHODES; LANTHANUM; ELECTRIC DISCHARGES; SPINELS; SOLID STATE PHYSICS; CATALYSTS; WASTES
009^X/EN
860^NMC 811 cathode constituent in lithium ion batteries is a promising candidate due to its high discharge capacity and low cost. However, it has significant drawbacks, such as high irreversible capacity loss, short cycle life, low thermal stability, prone to structural change from layered to spinel structure, thus lowering its electrochemical performance. Therefore, lanthanum dopants are used to prevent structural transformation. In this study, the synthesis of NMC 811 cathode precursor using solid state method which is the simplest method with low cost to produce nanometer-sized NMC cathode. The synthesis of NMC 811 cathode precursor utilizes used catalyst waste and low grade mineral ore as raw materials considering the decreasing availability of raw materials in nature due to increased exploitation. Therefore, this study was conducted to determine the effectiveness of the leaching process on spent catalysts for nickel, cobalt, and lanthanum and manganese mineral ore on the recovery of an element that will be used as a base material for the synthesis of NMC 811 lithium battery cathode precursors. In addition, it is also to determine the characterization of structural properties, morphology, and functional groups of NMC 811 lithium battery cathodes added with lanthanum in variations in lanthanum composition. The characterizations used are XRF (X-Ray Fluorescence), XRD (X-Ray Diffraction), FT-IR (Fourier Transform-Infra Red), and SEM (Scanning Electron Microscope). Based on the XRF (X-Ray Fluorescence) results, the recovery results of nickel, cobalt, manganese, and lanthanum were 93.36 %; 89.28 %; 90.65 %; and 99.53 %. XRD (X-Ray Diffraction) results in the addition of increasing lanthanum concentrations, causing structural transformation from layer to rock-salt. FT-IR (Fourier Transform-Infra Red) results on lanthanum concentration variations did not have significant differences, but there were still C-O groups that indicated the presence of impurities. SEM (Scanning Electron Microscope) results on the hexagonal layer structure and on the cubic rock-salt structure. CV (Cyclic Voltametry) results the higher the La dopant, the narrower the peak which indicates fast Li+ diffusion. EIS (Electrochemical Impedance Spectroscopy) results the higher the La dopant, the smaller the Warburg (#Greek Small Letter Sigma#) value which indicates fast Li+ diffusion. Galvanostatic Charge-Discharge results have a stable discharge capacity after 100 cycles. (author)
001^ID2500014
008^S62/01/I/M/U
009^M
100^Fadhlurrohman, Muhammad Dzaki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis and characterization of Tc-99m labeled MgFe_2O_4 nanoparticles with potential as dual-imaging SPECT/MRI radiopharmaceuticals
230^Sintesis dan karakterisasi nanopartikel MgFe_2O_4 tertanda Tc-99m yang berpotensi sebagai radiofarmaka dual-imaging SPECT/MRI
300^INIS-ID--0073
403^2023
500^82 p.
600^(IN)
610^73 refs.; 21 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; TECHNETIUM 99; NANOPARTICLES; IMAGES; RADIOPHARMACEUTICALS; SPECTROSCOPY; NEOPLASMS; RISE; MAGNETIC PROPERTIES; SIMULATION
009^X/EN
860^The incidence of cancer is on the rise, reaching 1.79 per 1000 population. Delayed diagnosis poses challenges in curbing this rate. MgFe_2O_4 MNPs with magnetic properties hold potential as MRI contrast agents within the body. The different synthesis methods of MgFe_2O_4 can impact its physical characteristics. Presently, coprecipitation and sol-gel methods are the most convenient to employ. FTIR results confirm the advantages of using citric acid as a synthesis reaction fuel and NH_4OH as a base source, leaving no residues after calcination. Verification of MgFe_2O_4 crystal formation was achieved through XRD results simulated with JCPDS 04-003-2900. VSM results demonstrate magnetic saturation strengths of the products at 18.5; 21.4; and 11.9 emu/g, making them suitable as MRI contrast agents. HSA and chitosan effectively coat MNPs, as observed in the FTIR results. FTIR results also exhibit the bonding between folic acid and MNPs coated with HSA and chitosan, with folic acid serving as an efficient and selective targeting agent for all cancer types. Labeling MNPs with "9"9"mTc yields a purity above 90 %, surpassing the purity standard of Tc-based radiopharmaceuticals. The binding of "9"9"mTc and folic acid as a cancer-targeting compound offers the potential for the product to be used as an SPECT imaging agent for cancer, thereby supporting dual SPECT/MRI imaging techniques. (author)
001^ID2500015
008^S54/01/I/M/U
009^M
100^Zain, Muhammad Khoirul
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effectiveness of decontamination of Cobalt-60 using peel-off gel from polyvinyl alcohol
230^Efektivitas dekontaminasi Cobalt-60 menggunakan gel kelupas dari bahan polyvinyl alkohol
300^INIS-ID--0074
403^2023
500^70 p.
600^(IN)
610^31 refs.; 18 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DECONTAMINATION; COBALT 60; GELS; PVA; RADIOISOTOPES; HAZARDS; POLYMERS; ENVIRONMENT; GLASS; CERAMICS; METALS
009^X/EN
860^Cobalt-60 radionuclide is a radioisotope with a half-life of 5.27 years. Cobalt-60 has many benefits for life, but on the other hand it can pose a contamination hazard if not properly monitored. To remove Cobalt-60 contamination, an effective decontamination technique is needed. One of the decontamination techniques being developed is using a chemical gel. The chemical gel that will be used in this study is based on Polyvinyl Alcohol (PVA). This polymer was chosen because it is non-toxic, soluble in water, safe for the environment, and easy to obtain. This research was conducted by pouring PVA solutions with various variations %EDTA (0,1,2,3, and 5 %) for 24 hours on glass, ceramic, and metal plate that had been dripped with 50 microliters of Cobalt-60 contaminant. From the results of the study, the best composition was solution the percentage of 15 % PVA (w/v aquadest), 2 % EDTA (w/v aquadest), glycerol (1%wt), and ethanol 88 % (w/v aquadest) which had an effectiveness value of 96.89 % on ceramic plate, 98.10 % on glass plate, and 94.09 % on metal plate. The decontamination mechanism is known through the binding of cobalt ions with EDTA through a chemical cross-linking mechanism. This is proven from FTIR result at wave number 1050 cm"-"1 comes from the stretching vibration of Co-O and the absorption peak of 1270 cm"-"1 is thought to come from the stretching vibration of Co-N due to coordinative covalent bonds in the compound [Co(EDTA)]-. The addition of EDTA is proven to increase the effectiveness of Cobalt-60 decontamination. (author)
001^ID2500016
008^S60/01/I/M/U
009^M
100^Umardi, Mulangsari Fadzia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effects of moderate dose of food irradiation on the quality of cashew nut (Anacardium occidentale L.) pecel sauce
230^Pengaruh iradiasi pangan dosis sedang terhadap kualitas sambal pecel kacang mete (Anacardium occidentale L.)
300^INIS-ID--0075
403^2023
500^70 p.
600^(IN)
610^98 refs.; 15 figs.; 22 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DOSES; FOOD PROCESSING; IRRADIATION; NUTS; NUTRITIONAL DEFICIENCY; INDONESIA; PRESERVATION; MICROORGANISMS; STORAGE
009^X/EN
860^Cashew nuts (Anacardium occidentale L.) have high nutritional and economic value. Cashew nuts pecel sauce is a popular traditional Indonesian salad dressing that has been produced commercially. Irradiation is a non-thermal food preservation process that can inhibit the growth of spoilage and pathogenic microorganisms. The purpose of this study was to determine the effect of moderate doses of irradiation on the chemical properties and rancidity of cashew nut pecel sauce. In this study, gamma irradiation was carried out with a combination of frozen storage of cashew nut sauce with three variations (original, spicy, and extra spicy). The source of gamma irradiation used was "6"0Co with irradiation doses of 0 kGy, 5 kGy and 10 kGy. Parameters tested were proximate analysis (moisture content, ash content, fat content, protein content, carbohydrate content), pH value, water activity (aw) and TBA (Thiobarbituric Acid) test. This study was arranged using a factorial completely randomized design (CRD) with two factors and three replications. Data processing techniques based on analysis of variance (ANOVA) and Duncan Multiple Range Test (DMRT) with a confidence level of 95 %.The results showed that moderate doses of irradiation had no effect on water content, ash content, fat content, and carbohydrate content, but had an effect on water activity (aw), pH value, protein content, and TBA value of cashew nut pecel sauce. (author)
001^ID2500017
008^S42/01/I/M/U
009^M
100^Afra, Nadila
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^HAZOP analysis and determination of safety integrity level in POLTEK NUKLIR - BRIN mini plant DCS
230^Analisis HAZOP dan penentuan safety integrity level pada mini plant DCS POLTEK NUKLIR - BRIN
300^INIS-ID--0076
403^2023
500^113 p.
600^(IN)
610^42 refs.; 20 figs.; 57 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SAFETY; FUEL INTEGRITY; PLANTS; SIMULATION; SOLVENT EXTRACTION; MEASURING INSTRUMENTS; LIQUIDS; TANKS; MIXING; HAZARDS
009^X/EN
860^POLTEK NUKLIR-BRIN has a Distributed Control System laboratory facility with a miniplant that is provided for industrial process trial simulations using the liquid-liquid mixing model by mixing 2 pieces of liquid material through 2 stages, namely the preparation process in the form of measuring the volume of liquid material to be put into the mixing tank by using an agitator as a stirrer so that the fluid becomes homogeneous it is controlled using DCS with several parameters that can be measured and controlled. This facility is only for learning, so the fluid used is water. This mixing tank was developed with a heating device which is expected to heat the fluid up to 125 #Degree Sign#C. This study aims to analyze the hazard potential and risk level with the HAZOP study which refers to the risk matrix based on Standard AS/NZS 4360:2004 and determines the value of safety integrity level on the POLTEK NUKLIR-BRIN miniplant to determine the level of system security when operating equipment at the facility. From the analysis results obtained 12 study points (nodes) with 39 possible process deviations caused by 56 failures in the tool consisting of 30 potential hazards in the low risk category (low risk) and 25 potential hazards in the medium risk category (medium risk). Control recommendations for the low risk hazard category can be carried out routinely such as calibrating tools and carrying out preventive maintenance on a regular basis, at medium risk apart from requiring equipment maintenance such as periodic calibration, inspection and monitoring it is also necessary to add recommendations to prevent possible deviations from occurring. Based on the analysis and calculations, the SIL value was obtained at the DCS POLTEK NUKLIR-BRIN miniplant facility with the main tool mixing tank having 2 protection systems, namely in the mixing process where the SIL value is at level 2 and in the fluid heating process with the SIL value which is also at level 1, if you want to achieve a higher SIL value, it can be recommended to add a security system (SIF) in the form of a smoke detection alarm around the heater or replace the heater installation so that there is an increase in the security protection system (SIS) in the DCS laboratory miniplant of POLTEK NUKLIR-BRIN. (author)
001^ID2500018
008^S62/01/I/M/U
009^M
100^Pranisuari, Ni Made Yuktikamura Galih
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis and radiolabeling of ["1"7"7Lu]Lu-DTPA-NH_2 complex for targeted cancer cell therapy
230^Sintesis dan radiolabeling kompleks ["1"7"7Lu]Lu-DTPA-NH_2 untuk terapi target sel kanker
300^INIS-ID--0077
403^2023
500^87 p.
600^(IN)
610^58 refs.; 33 figs.; 27 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; PRODUCT LABELING; NEOPLASMS; TUMOR CELLS; RADIOPHARMACEUTICALS; LUTETIUM 177; THERAPY; LIGANDS; AMINES; INCUBATION
009^X/EN
860^The development of ["1"7"7Lu]Lu-DTPA-NH_2 compound as a novel radiopharmaceutical for cancer cell radiotherapy aims to broaden the spectrum of cancer treatment options available to patients, making optimal cancer treatment accessible to all cancer patients in Indonesia. Lutetium-177 is a radionuclide emitting both #beta##En Dash# and #gamma# radiation, complexed with a free amine which is capable of binding to cancer cells. This complexation is facilitated by a ligand commonly used for radiometals, namely DTPA. An organic synthesis process to obtain the DTPA-NH_2 complex is carried out in two stages: the amine deprotection stage and the complexation between DTPA and NH_2. The deprotection process is performed to obtain the free amine, with the best results achieved at pH 3 and a reaction time of 24 hours at room temperature. The complexation of DTPA with the free amine to yield the DTPA-NH_2 compound yields the best results at pH 5 and an incubation time of 24 hours at 37 #Degree Sign#C. However, successful radiolabeling of the ["1"7"7Lu]Lu-DTPA-NH_2 complex has not yet been achieved across all variations, as the ["1"7"7Lu]Lu-DTPA-NH_2 peak could not be identified in the radiochromatogram obtained from all attempted radiolabeling variations. Therefore, a radiopharmaceutical ["1"7"7Lu]Lu-DTPA-NH_2 that meets the requirements of the Indonesian National Agency of Drug and Food Control (CPOB), where the radiochemical purity value must reach 95 %, has not been formed yet. Consequently, optimization of the radiolabeling process and verification of the presence of DTPA in the sample compound used for the radiolabeling process are necessary. (author)
001^ID2500019
008^S12/01/I/M/U
009^M
100^Adikartika, Patricia Tiara
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Batik wastewater treatment using Bacillus subtilis microorganisms and gamma irradiation
230^Pengolahan limbah cair batik dengan mikroorganisme Bacillus subtilis dan iradiasi gamma
300^INIS-ID--0078
403^2023
500^74 p.
600^(IN)
610^21 refs.; 23 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^WASTE WATER; PSEUDOMONAS; ELECTRON BEAMS; IRRADIATION; INDONESIA; POLLUTION; LIQUID WASTES; PH VALUE; WET OXIDATION PROCESSES; REGULATIONS
009^X/EN
860^Batik is a traditional Indonesian fabric art that uses dyeing techniques. In the batik dyeing process, liquid waste containing heavy metals and synthetic materials that are difficult to decompose is generated. The city of Pekalongan is the largest producer of batik crafts in Indonesia, with 1457 registered batik small and medium-sized enterprises (UMKM), resulting in a significant amount of waste being produced. The disposal of a large amount of waste directly into the environment disrupts the ecosystem, leading to a lack of suitable surface water sources in Pekalongan.This research utilizes the microorganism Bacillus subtilis and gamma irradiation to degrade simulated batik waste from reumazol color mixtures. Process variables such as the addition of HCl and H_2O_2, as well as variations in gamma irradiation doses, are optimized to achieve maximum degradation. The efficiency of the biological and irradiation processes is evaluated based on the color degradation level using a UV-Vis spectrophotometer. The obtained kinetics of color degradation for the simulated liquid waste are 0.3455 (C_A)"1 for the biological process, 0.2493 (C_A)"1 for gamma irradiation, and 0.2104 (C_A)"1 for the combination of microorganism and gamma irradiation. Water quality parameters are analyzed based on pH, BOD, COD, TSS, and toxicity testing. The best results were obtained after treating the water biologically for three (3) days and then continuing with gamma irradiation at a dose of 20 kGy. At this dose, the following values were achieved: pH 7.14, BOD 82.3, COD 1490.273, and TSS 51. The toxicity level decreased from #Double Prime#very high acute toxicity#Double Prime# to #Double Prime#high acute toxicity#Double Prime#. However, these results still do not meet the specified quality standards, indicating that further research is required. (author)
001^ID2500020
008^S60/01/I/M/U
009^M
100^AD, Puput Melati
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Optimization of DNA extraction method in mutant rice using modified potassium acetate
230^Optimasi metode ekstraksi DNA pada padi mutan menggunakan potassium acetate yang dimodifikasi
300^INIS-ID--0079
403^2023
500^76 p.
600^(IN)
610^53 refs.; 18 figs.; 12 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DNA; EXTRACTION; MUTANTS; RADIATION INDUCED MUTANTS; RICE; POTASSIUM; ACETATES; PLANT BREEDING; GAMMA RADIATION; MUTAGENS
009^X/EN
860^In the application of nuclear techniques in plant breeding, especially the use of gamma rays as physical mutagens will cause directly or indirectly changes in genetic material (DNA). These changes can include changes in the composition of the DNA molecules, bases and also breakage of DNA chains. The genetic diversity formed due tot of the radiation mutagenesis has the opportunity to improve plant genetic characters to produce the better new plant genotypes. Mutant genotype obtained need to be molecularly identified, to ensure that changes have occurred at the genetic level, not due to phenotype changes of environmental factors. Molecular analysis for the identification of genetic diversity of mutant genotypes need total DNA. This study aimed to determine the best DNA extraction method using potassium acetate with high purity total DNA yield. The mutant rice leaf used is of the result of gamma ray induction and control (parent plants). Four gamma-ray induced mutant rice are Rojolele Srinar, Rojolele Srinuk, Payo Iluk so, Payo Ngarayak and two control (parent plants) namely Rojolele and Payo. The potassium acetate DNA extraction method modified the buffer solution, that is relatively toxic chemical compound will be eliminated. In buffer solution used percent variation of Sodium Dodecyl Sulphate (SDS) were 5 %, 10 %, 15 % and 20 %, while variations of potassium acetate addition were 3 M and 5 M. Based on DNA quantity and quality measurement using Nanodrop#Registered Sign#ND1000 spectrophotometer, DNA concentration on the effect of variation SDS 5 %, SDS 10 %, SDS 15 % and SDS 20 % showed sequential DNA concentration values were 186,098#+-#73,421 ng/#Greek Small Letter Mu#L, 169,260#+-#79,239 ng/#Greek Small Letter Mu#L, 182,816#+-#77,554 ng/#Greek Small Letter Mu#L and 180,243#+-#54,211 ng/#Greek Small Letter Mu#L, while the sequential purity were 1,963#+-#0,026; 1,965#+-#0,031; 1,964#+-#0,031; and 1,961#+-#0,034. The sequential DNA concentration of addition of 3 M and 5 M potassium acetate were 190,242#+-#69,735 ng/#Greek Small Letter Mu#L dan 168,966#+-#72,055 ng/#Greek Small Letter Mu#L, while DNA purity were 1,970#+-#0,028 and 1,957#+-#0,033. The variation percent SDS on DNA quantity and quality hasn't significant effect indicated by a P-Value > 0,05. In the other side, the concentration of potassium acetate on quantity and quality has a significant effect indicated by P-Value < 0,005. Despite some treatment hasn't significant effect, but from an economical point of view and according to quality requirements, the best extraction method based on this study is 5 % SDS with the addition 3 M potassium acetate. (author)
001^ID2500021
008^S61/01/I/M/U
009^M
100^Merdekawati, Rima Agustin
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of external and internal radiation exposure from building materials in Jabodetabek area
230^Analisis paparan radiasi eksternal dan internal dari bahan bangunan di wilayah Jabodetabek
300^INIS-ID--0080
403^2023
500^162 p.
600^(IN)
610^85 refs.; 20 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^BIOLOGICAL EFFECTS; DOSES; RADIATION EFFECTS; BUILDING MATERIALS; DOSE RATES; GAMMA SPECTROSCOPY; RADIOACTIVITY; RADON
009^X/EN
860^Building materials used to build houses such as cement, bricks, sand and aerated lightweight concrete come from soil and rocks that contain natural radionuclides, especially Uranium ("2"3"8U), Thorium ("2"3"2Th) and Potassium ("4"0K). Natural radionuclides contained in building materials can provide an external radiation hazard in the form of gamma radiation emitted from the decay of radionuclides present in the material ("2"3"8U, "2"3"2Th and "4"0K) and an internal radiation hazard caused by inhalation of the "2"2"6Ra decay product, namely radon gas ("2"2"2Rn). Knowledge of radionuclide concentrations in building materials is very important in estimating the dose received by building occupants because most people spend 80 % of their time indoors. This research was conducted to determine the concentration of natural radionuclide activity contained in building materials, to calculate external and internal doses as well as the annual effective dose received from building materials. Measurement of natural radionuclide activity concentrations from the Uranium ("2"3"8U) decay series or Radium ("2"2"6Ra) decay series, Thorium ("2"3"2Th) decay series and Potassium ("4"0K) was carried out using a Gamma Spectrometer while measuring the concentration of "2"2"2Rn activity using a RAD7 tool. In this study, measurements of the concentration of natural radionuclide activity were carried out on 81 samples of building materials consisting of sand (19), bricks (13), lightweight concrete (33) obtained from Jabodetabek area. Based on the research results, the activity concentration of "2"2"6Ra ranged from 4 - 107 Bq/kg with an average of 34 Bq/kg; "2"3"2Th ranges from 1 - 85 Bq/kg with an average of 21 Bq/kg; "4"0K ranges from 20 Bq/kg - 940 Bq/kg with an average of 217 Bq/kg. The average concentrations of "2"3"2Th and "4"0K were lower than the world averages 45 Bq/kg and 412 Bq/kg, while the average values for the concentrations of "2"2"6Ra were slightly higher than the world average values 32 Bq/kg. The average value of the effective dose due to external exposure to building materials is 0.45 mSv, not exceeding the world average of 0.48 mSv. The activity concentration of "2"2"2Rn ranged from 13-895 Bq/m"3 with an average of 116 Bq/m"3. The average value of the effective dose due to inhalation of "2"2"2Rn from building materials is 4,11 mSv. The annual effective dose received from building materials in the Jabodetabek area has a value range between 0,72 - 23,21 mSv/year with an average of 4,56 mSv. (author)
001^ID2500022
008^S37/01/I/M/U
009^M
100^Assegaf, Rizal Nur
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis and characterization of low tenorm zirconium oxycloride using micronized zirconium silicate type MC-101 from PT Monokem Surya
230^Sintesis dan karakterisasi zirkonium oksiklorida rendah tenorm dengan micronized zirconium silicate tipe MC-101 dari PT Monokem Surya
300^INIS-ID--0081
403^2023
500^74 p.
600^(IN)
610^59 refs.; 18 figs.; 18 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; ZIRCONIUM; ZIRCONIUM SILICATES; INDONESIA; COMMERCIALIZATION; KINETICS; LEACHING; MELTING; WATER; SODIUM
009^X/EN
860^Zircon sand in Indonesia has not yet been processed into factory-scale zirconium products, but is only sold as zircon concentrate. Commercial zirconium products have provisions for a U+Th content of < 500 ppm with an interventional exposure of < 1 Bq/g. To reduce the U+Th content, it is necessary to process zircon into zirconium oxychloride (ZOC). This research describes the synthesis process and the results of the characterization of ZOC using micronized zirconium silicate type MC-101 from PT Monokem Surya, the effects of temperature and time variations, and looking for a suitable kinetic model for the HCl leaching process. The processing begins with melting zircon with NaOH with a mole ratio of 1 (zircon): 4 (NaOH) at 750 #Degree Sign#C for 3 hours. The smelt was then leached with water at a ratio of 5 kg (melted product): 90 L (water), temperature 60 #Degree Sign#C for 3 hours, stirring speed 150 rpm with 4 repetitions. Sodium zirconate as a result of water leaching was then converted into ZOC by leaching 4N HCl at various temperatures (30, 40, 50, 60, 90 #Degree Sign#C) and reaction times (15, 30, 45, 90, 150 minutes). The ZOC synthesis results were then characterized using XRF, XRD, FTIR, and Alpha-Beta Spectrometer. The data obtained from XRF is used to calculate the kinetics of HCl leaching using the shrinking core model (SCM) approach. The results of the synthesis of ZOC in this study had a concentration of 27.962 % close to the commercial zircon content of 28 % with a U+Th content of < 500 ppm so that it can be said that ZOC in this study was TENORM free. ZOC compounds have been confirmed by analysis and interpretation of FTIR data by comparing commercial products. On increasing the HCl leaching temperature from 60 #Degree Sign#C to 90 #Degree Sign#C the reaction rate constant increased significantly from 0.000006/s to 0.000007/s. The kinetics of the leaching reaction of sodium zirconate using HCl in this study followed the kinetics model of the ash layer diffusion control with an activation energy of 3.0861 kJ/mol. (author)
001^ID2500023
008^S37/01/I/M/U
009^M
100^Rafifah, Safina
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis of low tenorm zirconium hydroxide nanoparticles using the sol-gel method
230^Sintesis nanopartikel zirkonium hidroksida rendah tenorm dengan metode sol-gel
300^INIS-ID--0082
403^2023
500^61 p.
600^(IN)
610^28 refs.; 32 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; ZIRCONIUM; ZIRCONIUM SILICATES; NANOPARTICLES; SOL-GEL PROCESS; MINERALS; INDONESIA; IMPLANTS; HOMOGENEOUS CATALYSIS; RADIOACTIVITY
009^X/EN
860^The existence of zircon minerals (ZrSiO_4) derived from zircon sand has considerable potential in Indonesia but still has not received an increase in added value. One of the zircon sand preparations is zirconium hydroxide (ZOH) which can be developed as a bioimplant and as an intermediate for the zirconium compound industry, but action needs to be taken to reduce the radioactivity of zircon due to TENORM. In the synthesis of low zirconium hydroxide nanoparticles, TENORM sol-gel method is used to form nanoscale particle sizes while forming homogeneous morphological appearances. This study was conducted to determine the effect of variations in IPA weight (1:2 ; 1:4 ; and 1:6) and pH (2, 4, and 6) as well as optimal synthesis conditions compared to conventional ZOH methods. The more IPA results, the smaller the ZOH particle size and the smaller the ZrO_2 content, while the higher the pH, the larger the particle size and the higher the ZrO_2 level. The optimum condition is found at 1:6 pH 6 with a Zr(Hf)O_2 content of 53.62 % having an amorphous phase with a non-sharp diffraction peak at an angle of 2#Greek Small Letter Theta# of about 31.6#Degree Sign# and a homogeneous particle size of 369.9 nm then there is a peak of the FTIR absorption band at wavenumber 1622.1 cm"-"1 which is characteristic of the vibration of the #En Dash#OH group at Zr(OH)_4. The levels of U and Th in ZOC and ZOH sol-gel and conventional methods are less than the detection limit of the XRF tool, which is 0.01 %. ZOH sol-gel and conventional methods have differences in particle size where sol-gel ZOH has a particle size with a range of 369.9-674.5 nm (nanometers) which is homogeneous on average, while conventional ZOH has a large size of 205.2 #Greek Small Letter Mu#m (micrometers) and is not homogeneous. (author)
001^ID2500024
008^S09/01/I/M/U
009^M
100^Jelita, Silvia Happy
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Pre-design biodiesel plant from waste cooking oil using electrolysis method
230^Pra rancangan pabrik biodiesel dari minyak jelantah dengan metode elektrolisis
300^INIS-ID--0083
403^2023
500^175 p.
600^(IN)
610^36 refs.; 17 figs.; 53 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^BIODIESEL FUELS; FOOD PROCESSING; WASTE OILS; METHANOL; COST; PLANTS; ELECTROLYSIS; DIESEL FUELS; INDONESIA; TRIGLYCERIDES
009^X/EN
860^Biodiesel is an alternative energy source developed for diesel fuel based on the government's mandate through Minister of Energy and Mineral Resources Regulation Number 12 of 2015 with the proportion of a mixture of biodiesel and diesel B35 by 2023. By looking at the potential for used cooking oil in Indonesia, it can be used as raw material for biodiesel because it contains fat (triglycerides). Biodiesel production from waste cooking oil can be carried out through the electrolysis transesterification method and can be developed into a predesigned biodiesel plant. The plant id designed to be built in 2026 with a production capacity of 130,000 tons/year in Subang, West Java. This plant will be operated continuously for 330 days/year and 24 hours/day. The pre-design of the biodiesel plant aims to determine the technical feasibility and economic evaluation as well as obtain the results of the pre-designed biodiesel plant from waste cooking oil by the electrolysis method. There are three main stages of making biodiesel from waste cooking oil, including the raw material preparation stage, the transesterification reaction stage, and the purification stage. The transesterification-electrolysis reaction step was carried out by mixing the raw materials with the ratio of waste cooking oil: methanol (1:6), 0.53 % wt NaOH/chitosan-Fe_3O_4 catalyst, and water 2 % wt. The reaction was carried out in a batch reactor at 25 #Degree Sign#C with a pressure of 1 atm for 5 hours with a conversion of 87 %. The design of the biodiesel plant is feasible to be built. This can be proven by the suitability of the technical feasibility obtained by the pre-designed biodiesel plant using six primary process equipment, including reactor, decanter 1, evaporator, decanter 2, flash drum, and distillation tower while the calculation of the economic evaluation obtained the BEP (breakeven point) percentage of 42 %, SDP (shut down point) percentage of 27 %, ROI (return on investment) before tax percentage of 49 %, ROI (return on investment) after tax percentage of 34 %, POT (pay out time) before tax for 1,7 years, POT (pay out time) after tax for 2,3 years, and DCFR (Discounted Cash Flow Rate) percentage of 19,1 %. With a profit before tax of IDR216.497.502.165/year and a profit after tax of IDR151.548.251.561/year. (author)
001^ID2500025
008^S12/01/I/M/U
009^M
100^Salma, Sufi Adzkia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The diffusion ability evaluation of Cs-137 in compacted soil and bentonite under groundwater-saturated condition
230^Evaluasi kemampuan difusi Cs-137 pada tanah dan bentonit dengan penjenuhan air tanah
300^INIS-ID--0084
403^2023
500^165 p.
600^(IN)
610^184 refs.; 52 figs.; 44 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^CESIUM 137; DIFFUSION; EVALUATION; COMPACTING; SOILS; BENTONITE; GROUNDWATER RECHARGE; RADIOACTIVE WASTES; WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES
009^X/EN
860^The increase in the amount of radioactive waste in Indonesia has resulted in a plan to build a disposal site which will be managed by the Deputy for Nuclear Facility Management - National Research and Innovation Agency (DPFK - BRIN) and is part of the research which is covered by the Center for Research and Technology of the Nuclear Fuel Cycle and Radioactive Waste (PRTDBBNLR). One of the candidate locations for the disposal site is DH-2 in the Serpong Nuclear Area with the planned type of disposal being Near Surface Disposal (NSD) according to the type of waste received by DPFK - BRIN. One aspect that needs to be studied in the construction of disposal facilities is the safety aspect, including a multi-barrier system consisting of natural (soil) and engineered barriers (bentonite). Therefore, this study evaluated the ability of the barrier layer to the possibility of release or migration of Cesium-137 from the repository to the unsaturated zone based on the vertical diffusion of radionuclides in groundwater saturation media based on variations in time and density. The samples used were soil from DH-2 from the Serpong Nuclear Center (SNC), bentonite from Santrijaya Village - Tasikmalaya, and Cs-137. This study focused on the effect of metal ions in groundwater on the diffusion ability of Cs-137 so the simulated groundwater used was NaCl, KCl, CaCO_3, MgCl_2.6H_2O and FeCl_3-6H_2O of 19; 20; 50; 15 and 0.25 in ppm respectively. ICP-OES analysis showed the soil samples contained quite a high amount of iron (Fe) and the bentonite sample belonged to the moderate bentonite category, which is more likely to be considered in Ca-bentonite type (nonswelling bentonite). The MCA analysis of sample slices showed that the overall value of Da decreased as the density of the medium increased and the time variation did not affect the value of the diffusion coefficient, with the value of the diffusion coefficient Cs-137 in soil samples with time variations in the range of ~5.20 x 10"-"1"2 with slightly different values in range of <0.005 x 10"-"1"2. On the other hand, the value of the diffusion coefficient of Cs-137 under groundwater-saturated condition increases, although not significantly in the presence of other cations, when compared to the value of the diffusion coefficient of Cs-137 in identical study conducted using demin water. From the safety assessment scenario analysis using RESRAD Offsite, it can be assured that the scenario with bentonite from Tasikmalaya 0.3 m thick is the right choice to be considered in the disposal facility plan in SNC. The results of this study were expected to enrich information on the safety assessment program for the development of radioactive waste disposal sites in the SNC disposal site development program for NSD facility. (author)
001^ID2500026
008^S54/01/I/M/U
009^M
100^Hilal, Syamsul
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Characteristics of air particulates in the North Jakarta industrial area
230^Karakteristik partikulat udara di kawasan industri Jakarta Utara
300^INIS-ID--0085
403^2023
500^76 p.
600^(IN)
610^44 refs.; 35 figs.; 15 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^AIR; PARTICLES; PARTICULATES; RADIATION MONITORING; RADIOACTIVITY; RADIOISOTOPES; SAFETY; POLLUTANTS; TOXICITY; AIR POLLUTION; AIR POLLUTION MONITORING
009^X/EN
860^Particulate pollutants are the most toxic type of pollutants. DKI Jakarta as a metropolitan city has a high level of air pollution. The sampling location was carried out at Rusunawa Marunda, which is located in the industrial area of North Jakarta. The analysis process includes measuring the mass concentration of PM_2_._5 and PM_1_0, which are particulates measuring 0-2.5 #Greek Small Letter Mu#m (fine particles) and 2.5-10 #Greek Small Letter Mu#m (coarse particles), black carbon concentration, and multi-element content. Sampling took place over four months (February-May 2023) and 34 fine particulate and coarse particulate samples were obtained. The mass concentration analysis showed that the average PM_2_._5 and PM_1_0 were 10.75 #Greek Small Letter Mu#g/m"3 and 35.44 #Greek Small Letter Mu#g/m"3, respectively. These results are below the daily ambient air quality standards based on PP No. 22 of 2021. Meanwhile, the Air Pollutant Standard Index at the location is a medium category with PM_2_._5 and PM_1_0 values of 58.95 and 63.30. Analysis of black carbon concentration shows an average value of 1.38 #Greek Small Letter Mu#g/m"3 with a percentage of 13.46 %. The black carbon concentration was higher when sampling on weekdays (Monday-Friday) compared to holidays (Saturday-Sunday). Analysis of the multi-element content in PM_2_._5 shows that sulfur is the element with the highest concentration while in PM_2_,_5_-_1_0 the element silicon dominates. The main RCM compositions in PM_2_._5 obtained were sulfate 24.11 % and black carbon 13.46 % while in PM_2_,_5_-_1_0 soil dust dominated 25.07 %. (author)
001^ID2500027
008^S22/01/I/M/U
009^M
100^Amalia, Tazkia Nurfaaqih
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of potential hazards in the reactor dijesti pilot plant senotim sand processing DPLFRKST-BRIN Yogyakarta with hazard and operability study method
230^Analisis potensi bahaya pada reaktor dijesti pilot plant pengolahan pasir senotim DPLFRKST-BRIN Yogyakarta dengan metode hazard and operability study
300^INIS-ID--0086
403^2023
500^110 p.
600^(IN)
610^46 refs.; 18 figs.; 51 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^HAZARDS; REACTORS; PILOT PLANTS; SAND; TIN; MINING; RARE EARTHS; INDONESIA; RISK ASSESSMENT
009^X/EN
860^Senotim sand is one of the by-products of tin mining at PT Timah which still has economic value and contains Rare Earth Element (REE). In 2018, at PSTA-BATAN Yogyakarta, a project was initiated to build a pilot plant for the processing of senotim sand. The main ingredients in this process are concentrated H_2SO_4 and senotim sand, H_2SO_4 in a concentrated atmosphere reacting with high temperatures will cause H_2SO_4 to evaporate. Operating conditions and materials used are one of the triggers for potential hazards. The purpose of this study is to analyze potential hazards, analyze risks and determine risk levels, and develop control recommendations for potential hazards found. Analysis of potential hazards was carried out using the HAZOP method and risk assessment was carried out using a risk matrix based on the AS/NZS 4360:2004 Standard. From the analysis, there were 17 deviations and 26 failures on the tool with 24 failures with low risk level, 1 failure with medium risk level, and 1 failure with high risk level and no failures with extreme risk level. Control recommendations are prepared based on each failure on the tool. (author)
001^ID2500028
008^S60/01/I/M/U
009^M
100^Sakina, Zafira Naja
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effect of medium dose irradiation on quality characteristics of peanut (Arachis Hypogea L) sauce
230^Efek iradiasi pangan dosis sedang terhadap karakteristik bumbu pecel kacang tanah (Arachis Hypogea L)
300^INIS-ID--0087
403^2023
500^88 p.
600^(IN)
610^59 refs.; 8 figs.; 12 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DOSES; FOOD PROCESSING; IRRADIATION; NUTS; NUTRITIONAL DEFICIENCY; INDONESIA; PRESERVATION; MICROORGANISMS; STORAGE
009^X/EN
860^Bumbu pecel is an Indonesian spicy sauce that is used as the main sauce in pecel dishes which usually consist of boiled vegetables, rice, and complementary side dishes. Bumbu pecel is made from peanuts, chili, garlic, shrimp paste, sugar, salt, and other additional ingredients. Pecel sauce has been sold commercially in paste form, however, the disadvantage of this product is its short shelf life. One way to extend the shelf life of pecel sauce products is by applying irradiation technology. The purpose of this study was to evaluate the effect of medium dose food irradiation on the quality characteristics of peanut (Arachis Hypogea L) pecel sauce. Samples of peanut pecel sauce used a control dose of 0 kGy and the doses irradiated using cobalt-60 were 5 kGy and 10 kGy with procedures in accordance with SNI for medium dose food irradiation. The parameters observed were pH, water content, ash content, protein, fat, carbohydrate, water activity (a_w), and TBA (Thiobarbituric Acid) value. The results showed that food irradiation had no significant effect on pH, moisture content, ash content, protein, fat, carbohydrates, and water activity (a_w) while it had a significant effect on TBA (Thiobarbituric Acid) value. (author)
001^ID2500029
008^S37/01/I/M/U
009^M
100^Utami, Zahra Khalifah
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Synthesis and characterization low TENORM zirconia nano using polyethilen glikol 4000
230^Sintesis dan karakterisasi nano zirkonia rendah TENORM menggunakan templat polietilen glikol 4000
300^INIS-ID--0088
403^2023
500^83 p.
600^(IN)
610^34 refs.; 25 figs.; 26 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SYNTHESIS; ZIRCON; NANOTECHNOLOGY; ZIRCONIUM; BIOMEDICAL RADIOGRAPHY; URANIUM; THORIUM; REGULATIONS; RAW MATERIALS; RADIOACTIVITY
009^X/EN
860^Zirconia is a product of zirconium from zircon sand processing which has many uses in several fields, such as technology, industry, and biomedical fields. Nano-sized zirconia has attracted the attention of several researchers, so the need for nano zirconia products has increased. This is because nano zirconia has good phase and thermal stability. The content of TENORM (Technologically Enchanted Naturally Occurring Radioactive Material) in nano zirconia must be of low value with the U and Th series of 1 Bq/g based on BAPETEN Regulation No 9 of 2009. The precursor raw material used is a solution of zirconyl chloride (ZrOCl_2) which has been purified from the basic raw material micronized zirconium silicate MC 101 has standard specifications according to commercial solutions, namely ZrO_2+HfO_2 of 21,583 %; Fe_2O_3 of 0,00093 %; and TiO_2 of 0,016 % and a low radioactivity value of 0,319#+-#0,053 Bq/g for alpha and 1,671#+-#0,074 Bq/g for beta. In producing low TENORM nano zirconia in this study used 12,5 % NH_4OH as precipitation at a variation of pH 5-9. The results showed optimal conditions at pH 5 in the form of good crystals in the tetragonal phase with a crystal size of 14,97 nm and a ZrO_2+HfO_2 content of 96,072 % and smaller level of impurities with the interaction of hydrogen bonds between the precursor and the PEG polymer at the peak of the absorption band around the wavelength of 3423 cm"-"1 and the size particles of 253,1 nm. Likewise, measurements on variations in mole rations obtained good results at the PEG/Zr ratio at 2,5:15 with the results of the characterization in the form of a tetragonal crystalline phase with a large crystal size of 17,4 nm, has a concentration of ZrO_2+HfO_2 of 96,072 %, has intramolecular hydrogen bond functional groups at the peak of 3455,72 cm"-"1. However, a smaller and more homogeneous nano-sized particle occurred at a high PEG/Zr 4:15 composition of 174,6 nm. The temperature variation of the sonicated solution showed good ZrO_2 results at 40 #Degree Sign#C with a monoclinic crystalline phase of 15,4780 nm crystal size, has a ZrO_2+HfO_2 content of 97.53 % and a sharp peak ZrO bond intensity at wavelengths of 746.85-416.29 cm"-"1. In addition, ZrO_2 nano formed better at lower temperatures in the room atmosphere by 198.6 nm. (author)
001^ID2500030
008^S43/01/I/M/U
009^M
100^Alfiansyah, Ahmad
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Integration of monitoring and operation systems ion source in DECY-13 cyclotron
230^Integrasi sistem pemantauan dan operasi sumber ion pada siklotron DECY-13
300^INIS-ID--0089
403^2023
500^72 p.
600^(IN)
610^26 refs.; 47 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^IONS; CYCLOTRON RADIATION; CYCLOTRONS; PHOTON BEAMS; POSITRON COMPUTED TOMOGRAPHY; YIELDS; MONITORING; DECAY; CYCLIC ACCELERATORS; POSITRON BEAMS
009^X/EN
860^One of the supporting tools in nuclear medicine is a cyclotron, which is a cyclic accelerator used to accelerate particles and produce radioisotopes for use in Positron Emission Tomography (PET) technology. The Development of Experimental Cyclotron in Yogyakarta 13 MeV (DECY-13) is a cyclotron currently being developed by the Accelerator Technology Research Center and has several main components, one of which is the ion source. The ion source produces ions that will be accelerated to a specific energy to be directed at the target. In its operation, the ion source of the DECY-13 cyclotron is supported by several components, including the cooling system, vacuum system, magnet power supply (MPS), hydrogen gas flow system, and cathode power supply. These supporting components are currently separate, and operators are still manually monitoring the operation. Therefore, integration is needed between the supporting components of the ion source of the DECY-13 cyclotron and the hardware components, including the NI-9870 module, NI-9425 module, and NI-cRIO as the operation process controller, as well as LabVIEW for the software used. As a result, an integration program for the vacuum system, hydrogen gas flow system, and cooling system has been successfully created, with displayed data on the interface matching the data from each respective device. This integration program can thus be used for monitoring the operation of the DECY-13 cyclotron ion source. (author)
001^ID2500031
008^S43/01/I/M/U
009^M
100^Simamora, Anna Ria Rezki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of web based expert system for diagnosing malfunction Cockcroft walton generator of electron beam machine 350 keV / 10 mA using forward chaining method
230^Rancang bangun sistem pakar diagnosa kerusakan generator Cockcroft walton pada mesin berkas elektron 350 keV/10 mA dengan metode forward chaining berbasis web
300^INIS-ID--0090
403^2023
500^137 p.
600^(IN)
610^24 refs.; 26 figs.; 8 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; DIAGNOSIS; COCKCROFT-WALTON ACCELERATORS; ELECTRON BEAMS; DAMAGE; SYMPTOMS; CHAINS; COMPILED DATA
009^X/EN
860^In a system, the damage is unavoidable. In order not to disturb the processes in the system, it is necessary to detect as soon as possible the elements that are experiencing disturbances. Diagnosing damage and repairing, takes people who have experience and understand knowledge about damage, causes, symptoms, and how to repair the Cockcroft Walton Generator of 350 keV/10 mA Electron Beam Machine. However, in reality in the field, not all personnel have sufficient knowledge and experience related to this matter. Therefore, in this research, a system was built that could become a database of the knowledge and experience of an expert so that it could be used by other personnel in diagnosing damage to the Cockcroft Walton Generator in a short time. #Double High-Reversed-9 Quotation Mark#Design of Web Expert System for Diagnosing Damage Cockcroft Walton Generator of Electron Beam Machine 350 keV/10 mA using forward chaining method#Right Double Quotation Mark# was created by compiling a knowledge base obtained from interviews with experts and literature by implementing the Forward Chaining method by the facts that occur to determine the solution into a database stored in MySQL through PHP and Java script source code programming media. This research has successfully created a web-based expert system application to diagnose malfunctions and provide solutions for identified issues in the Generator Cockcroft Walton system of the 350 keV/10 mA Electron Beam Machine using the Forward Chaining method. (author)
001^ID2500032
008^S43/01/I/M/U
009^M
100^Azhar, Aufa Kholif Izzatu
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of a prototype electron source power supply for linear accelerator
230^Rancang bangun prototype catu daya sumber elektron pada linear akselerator
300^INIS-ID--0091
403^2023
500^56 p.
600^(IN)
610^15 refs.; 33 figs.; 3 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; ELECTRON SOURCES; POWER SUPPLIES; LINEAR ACCELERATORS; NUCLEAR MEDICINE; ACCELERATORS; PARTICLES; FILAMENTS; CALIBRATION
009^X/EN
860^The linear accelerator technology is a device used in medical, industrial, and research applications to accelerate charged particles such as electrons. One of the key components in a linear accelerator is the power supply for the electron filament source, where the filament current affects the number of electrons and the electron beam current. This research aims to design and develop a prototype of an adequate power supply for the electron source that can be integrated with a computer, replacing the variac power supply. This research utilizes the Arduino Mega2560 microcontroller and a Boost Buck DC-DC Converter. In this study, a power supply for the electron source filament based on the Arduino Mega was successfully developed, with a relative control system error of 19.21 %. Control errors can be influenced by several factors, including the operational characteristics of electronic components, component calibration, and component efficiency levels. (author)
001^ID2500033
008^S43/01/I/M/U
009^M
100^A'la, Azhar Abdul
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design a website of internet accelerator laboratory (IA-Lab) based on the laravel framework
230^Rancang bangun website internet accelerator laboratory (IA-Lab) berbasis framework laravel
300^INIS-ID--0092
403^2023
500^103 p.
600^(IN)
610^27 refs.; 40 figs.; 4 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WEBSITES; FERMILAB ACCELERATOR; ACCELERATORS; NUCLEAR ENGINEERING; LINEAR ACCELERATORS; VACUUM SYSTEMS; OPTICAL SYSTEMS; FILAMENTS; SIMULATION; PROGRAMMING
009^X/EN
860^In the current 4.0 era, the demand for data acquisition, data visualization, and data storage systems is rapidly growing, including in the field of nuclear engineering. One of the areas in nuclear engineering affected by this technological advancement is the accelerator department. The impact of this technological progress has led to the development of a web-based application called Internet Accelerator Laboratory (IA-Lab). In IA-Lab, parameters related to the Linear Accelerator (Linac), such as the vacuum system, optical system, and filament current system, are displayed. The objective of this research is to create the IA-Lab website using the Laravel framework. Additionally, the system design is performed using Unified Modeling Language (UML) and Data Flow Diagram (DFD), with PHP programming language and MySQL database. The result of this research is a web application that provides information about Linac and displays system acquisition data from Linac. Furthermore, functional, performance, security, and user evaluation tests have been conducted to evaluate the IA-Lab website. The final score of the user evaluation using the System Usability Scale (SUS) method indicates an average value of 75. (author)
001^ID2500034
008^S43/01/I/M/U
009^M
100^Pamungkas, Bayu
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and build data acquisition system of electron source and vacuum system of linac at PRTA - BRIN
230^Rancang bangun sistem akuisisi data sumber elektron dan sistem vakum untuk fasilitas linac di PRTA - BRIN
300^INIS-ID--0093
403^2023
500^82 p.
600^(IN)
610^35 refs.; 58 figs.; 18 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WEBSITES; FERMILAB ACCELERATOR; ACCELERATORS; NUCLEAR ENGINEERING; LINEAR ACCELERATORS; VACUUM SYSTEMS; OPTICAL SYSTEMS; FILAMENTS; SIMULATION; PROGRAMMING
009^X/EN
860^PRTA - BRIN has given linear accelerator (linac) facility from Cipto Mangunkusumo hospital. Mechanically, this linac is builded, but in instrumentation and control aspect, this linac is not builded yet duet o its complexity. The aim of this research is to design and built the data acquisition system of linac's electrons source and vacuum system of linac facility at PRTA - BRIN on Science and Technology Area in Yogyakarta using software of LabVIEW and MySQL database. In this research of the design and built of data acquisition system, data acquisition modules which is Adam 4017"+ and 4520 and TPG 300 could receive data of electrons source and level of vacuum and transmit it to computer using serial communication to display it in interface of LabVIEW and then be saved in MySQL database. To validate data acquisition program on this builded of data acquisition system, acquired data from program is compared with measured value from exist instrument. In this research, builded data acquisition system has the accuracy og 98 % at measured electron beam data and 100% on each read vacuum sensor. (author)
001^ID2500035
008^S43/01/I/M/U
009^M
100^Bomanarakasura, Dimas Febrian
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Implementation interoperability model in application prototype of nuclear instrumentation laboratory information system of Poltek Nuklir with laravel framework
230^Implementasi model interoperabilitas untuk aplikasi sistem informasi laboratorium instrumentasi nuklir Poltek Nuklir dengan laravel framework
300^INIS-ID--0094
403^2023
500^198 p.
600^(IN)
610^42 refs.; 117 figs.; 8 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WEBSITES; FERMILAB ACCELERATOR; ACCELERATORS; NUCLEAR ENGINEERING; LINEAR ACCELERATORS; VACUUM SYSTEMS; OPTICAL SYSTEMS; FILAMENTS; SIMULATION; PROGRAMMING
009^X/EN
860^This research aims to design and implement an interoperability model in the process of developing an information system for the Nuclear Instrumentation Laboratory Services of the Indonesian Nuclear Technology Polytechnic. The problem that occurs in this laboratory is that data management is not optimal because the data is stored in various platforms and cannot be accessed outside the laboratory. Information about radioisotopes is also needed in laboratory utilisation. So, in this research, a Laravel Framework-based Nuclear Instrumentation Laboratory information system has been developed with a prototype method that allows laboratory managers and users to manage data and information more easily. The application developed has been equipped with interoperability so that it is able to share data from and into the application using API. The application is supported with PHP, HTML, CSS, Javascript programming languages and uses MySQL as a database management system. The application has been tested with the black box method and passed 123 test cases, and the API created has a response performance of around 500 ms in form of JSON format. The developed system has implement interoperability to consume levels and radioactive decay from IAEA's API, then this system is be able to share stored data using REST API. (author)
001^ID2500036
008^S43/01/I/M/U
009^M
100^Atha, Farras Faishal
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and construction of PLC based combustion element position control system for gamma scanning system in Kartini Reactor
230^Rancang bangun sistem kendali posisi elemen bakar berbasis PLC untuk sistem gamma scanning pada Reaktor Kartini
300^INIS-ID--0095
403^2023
500^64 p.
600^(IN)
610^10 refs.; 40 figs.; 9 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; CONSTRUCTION; COMBUSTION; CONTROL SYSTEMS; KARTINI-PPNY REACTOR; FUEL ELEMENTS; CAT SCANNING; GAMMA RADIATION; COLLIMATORS; SCINTILLATION COUNTERS
009^X/EN
860^The Kartini Reactor always strives for development by continuously enhancing its internal systems to become more efficient in its operation. One of them is the Gamma Scanning system used to observe and analyze the fuel fraction distribution (burn-up) in nuclear fuel elements. The Gamma Scanning system consists of a collimator and scintillation detector, along with preamp devices and a computer to calculate the fuel fraction distribution within the fuel elements. Gamma rays emitted by fission product radionuclides in the fuel elements are counted to obtain the burn-up values. To determine the burn-up fraction along the fuel element, a fuel element manipulator is required, allowing the burn-up fraction in each part to be detected by the Gamma Scanning system. However, up to this point, the fuel element positioning during the Gamma Scanning process at the Kartini Reactor has been controlled manually and in an Open Loop manner, using UP and DOWN buttons. In this method, the accuracy of position control greatly depends on the operator's concentration level. To facilitate the operator's task, a control system has been developed that can move the fuel elements with a constant displacement interval in a Closed Loop manner. (author)
001^ID2500037
008^S21/01/I/M/U
009^M
100^Septawijaya, Gilang
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Modeling neutronic and thermal hydraulic aspects of NuScale reactor using point kinetic equation and mann's model with labview software
230^Pemodelan aspek neutronik dan termalhidraulik reaktor NuScale menggunakan persamaan kinetika reaktor titik dan model mann dengan perangkat lunak labview
300^INIS-ID--0096
403^2023
500^78 p.
600^(IN)
610^54 refs.; 55 figs.; 13 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SIMULATION; NEUTRONIC DAMAGE FUNCTIONS; THERMAL HYDRAULICS; REACTORS; KINETIC EQUATIONS; NUCLEAR POWER PLANTS; REGULATORY GUIDES; HUMAN POPULATIONS; TEMPERATURE CONTROL; MODERATORS
009^X/EN
860^The development plan for Nuclear Power Plants (NPPs) in Indonesia has been a widely discussed issue lately. One of the planned types of NPPs is the Small Modular Reactor (SMR), where the reactor has a capacity of less than 300 MWe and has a modular design. One of the SMR designs that has been approved by the U.S. Nuclear Regulatory Commission (NRC) is provided by the company NuScale. Human resource readiness is an essential aspect to consider before constructing an NPP. The core modeling of the NuScale reactor is a crucial component in developing an NPP simulator. The core modeling employs reactor kinetics point equations, while the thermal-hydraulic aspect utilizes the Mann model. The modeling results indicate that the relative error values for the control rod positions in Regulating 1, Regulating 2, Safety 1, and Safety 2 groups are 0.0007 %, 0.0016 %, 0.0025 %, and 0.0041 %, respectively. The fuel temperature is estimated to be 657 K with a relative error of 0.48 %, the inlet moderator temperature is 531 K with a relative error of 1.1 %, and the outlet moderator temperature is 592 K with an error of 0 %. During the SCRAM scenario, the reactor can be shut down by fully inserting all control rods into the reactor core. (author)
001^ID2500038
008^S42/01/I/M/U
009^M
100^Sitanggang, Gredynov
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of irradiation and projection process monitoring system based on web on CT X-Ray digital radiography prototypes at PRTDRAN - BRIN
230^Rancang bangun sistem monitoring proses penyinaran dan proyeksi berbasis web pada prototipe radiografi digital CT Sinar-X di PRTDRAN - BRIN
300^INIS-ID--0097
403^2023
500^129 p.
600^(IN)
610^42 refs.; 97 figs.; 13 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; IRRADIATION; REACTOR MONITORING SYSTEMS; WEBSITES; GAMMA RADIATION; GAMMA RADIOGRAPHY; DIGITAL SYSTEMS; NUCLEAR ENGINEERING; NONDESTRUCTIVE TESTING; PROGRAMMING; PROGRAMMING LANGUAGES
009^X/EN
860^the development of technology has now become an integral part of human routines. This can be seen in numerous sectors that utilize and leverage information technology to support their work, including the field of nuclear technology. In PRTDRAN (Pusat Riset Teknologi Deteksi Radiasi dan Analisis Nuklir) there are digital radiography tools used for quality testing, one of which is the NDT (Non-Destructive Test). NDT is a testing technique used to observe the product being tested in a way that does not damage these parts. In testing a product, it is done not only once so it takes quite a long time to find out the test results of the product being tested. To address this, a website has been created with the aim of providing information related to the testing process, allowing clients to understand the extent of the testing conducted on their objects. The development of this website follows the SDLC (Systems Development Life Cycle) method, starting with planning, analysis, design, implementation, testing, and management. The system utilizes a MySQL database, which is based on the results of previous tests conducted by PRTDRAN, and the backend is developed using the PHP programming language, while the front end is created using HTML, CSS, and JS. The monitoring system for test results is capable of displaying data related to the testing conducted on requested objects. Processing the data through this monitoring system can optimize data handling and turn it into valuable information. (author)
001^ID2500039
008^S21/01/I/M/U
009^M
100^Baihaqi, Handika Dito Aulia
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of reactivity insertion accident in Kartini Reactor using RELAP5 code
230^Analisis reactivity insertion accident pada Reaktor Kartini dengan menggunakan kode RELAP5
300^INIS-ID--0098
403^2023
500^51 p.
600^(IN)
610^32 refs.; 31 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^REACTIVITY; REACTIVITY INSERTIONS; ACCIDENTS; REACTOR ACCIDENTS; KARTINI-PPNY REACTOR; REACTORS; SAFETY; HAZARDS; CONTROL ELEMENTS; SIMULATION
009^X/EN
860^Kartini reactor is one of the nuclear reactors in Indonesia. In operating a reactor, it must be ensured that the reactor can operate safety, both under normal and abnormal conditions. In some abnormal conditions such as the case of reactivity insertion accident (RIA) it is very difficult to do experimentally considering the potential hazards that may occur. Therefore, in this study a model of the Kartini reactor was developed using the code RELAP5/SCDAP to be used in analyzing the safety level of the Kartini reactor when a reactivity insertion accident (RIA) occurred. This RIA case can be caused by pulling the control rod. Before starting the transient simulation due to RIA, steady state calculations have been carried out and validated on fuel temperature measurements with an error of around 1.94 %. The reactivity insertion was varied in 3 conditions, namely 0.5 $, 1.0 $, and 1.5 $. The reactivity insertion is given at the 10,000"t"h second for 5 seconds with constant insertion rate. In this simulation, 2 variations of scenarios were carried out, namely by activating the scram system and by not activating the scram system. The calculation results show that from the three reactivity insertions with and without the scram system, the fuel cladding temperature does not exceed the predetermined safety limits. (author)
001^ID2500040
008^S61/01/I/M/U
009^M
100^Harman
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of an automatic pH control system for "1"5"3Sm-EDTMP radiopharmaceutical preparation process using Arduino based PID control
230^Rancang bangun sistem kendali pH otomatis untuk proses preparasi radiofarmaka "1"5"3Sm-EDTMP menggunakan PID kontrol berbasis Arduino
300^INIS-ID--0099
403^2023
500^52 p.
600^(IN)
610^10 refs.; 29 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; SAMARIUM 153; RADIOPHARMACEUTICALS; CHEMICAL PREPARATION; PH VALUE; CONTROL SYSTEMS; PERSONNEL; SENSORS; ALGORITHMS; INJECTION; REGULATIONS
009^X/EN
860^PH adjustment is one of the crucial processes in the production of the radiotherapeutic agent "1"5"3Sm-EDTMP to maintain it within the range of 7 - 8.5. Currently, this process relies on human intervention. In order to replace the human role, an automated pH control system design is developed using PID control. This device design employs a PH-4502C sensor to measure pH and a peristaltic pump controlled by an Arduino Uno microcontroller with a PID algorithm to regulate the injection of acid and base solutions into the system. The tested solution does not employ "1"5"3Sm-EDTMP; instead, it uses a mixture of HCl and NaOH with a volume of 30 ml contained in a 50 ml beaker. Solutions of HCl and NaOH at 1 Molar each, diluted in 180 milliliters of water, are utilized to control the pH of the solution. Tuning the parameters Kp, Ki, and Kd through trial and error yielded a steady-state error of 1.14 % with a settling time of 70 seconds and an overshoot of 9.2 %. (author)
001^ID2500041
008^S43/01/I/M/U
009^M
100^Kurniawan, Ilkham
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Software design of directional magnetic field measurement system radial and angular of DECY-13 cyclotron
230^Rancang bangun perangkat lunak sistem pengukuran medan magnet arah radial dan angular siklotron DECY-13
300^INIS-ID--0100
403^2023
500^86 p.
600^(IN)
610^45 refs.; 50 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; MAGNETIC FIELDS; ON-LINE MEASUREMENT SYSTEMS; SPATIAL DISTRIBUTION; ANGULAR DISTRIBUTION; CYCLOTRONS; ACCELERATORS; PARTICLES; ISOCHRONOUS CYCLOTRONS; PROGRAMMING
009^X/EN
860^The Development of the Experimental Cyclotron in Yogyakarta - 13 MeV (DECY-13) is a cyclotron currently being developed by the Accelerator Technology Research Center (PRTA). The DECY-13 cyclotron consists of various main components, one of which is the magnet system. This magnet system generates a specific magnetic field strength that serves to bend and focus particle beams to achieve an energy target of 13 MeV. During the design phase, the magnet system is engineered to meet isochronous criteria. After the design phase is completed, validation between the design and fabrication is carried out to ensure isochronous standards are met. One of the methods involves measuring the magnetic field at various points, known as magnetic field mapping. Hence, a device is required to map the magnetic field of the DECY-13 cyclotron. This device is divided into two main systems: the mechanical system and the control instrumentation system (SIK). The mechanical system has been completed and thus requires the SIK to automate the mechanical system's movement. The development of the SIK employs LabVIEW software and is divided into two stages: programming the control of the mechanical system and creating a Human Machine Interface (HMI). The HMI serves as a visualization of the system to facilitate the use of the created SIK. The program testing is conducted in two stages: testing the conformity of angular and radial movements, as well as testing the overall program conformity. The conformity of movements indicates that angular and radial values under actual conditions deviate by 4.43 % and 6.1 %, respectively, from the designated values. Meanwhile, the testing of data storage results in a deviation of 3 % from the expected values. The automated mapping program reveals differences of 7 % and 9 % for grid iteration and program iteration, respectively. It is concluded that a software tool has successfully been developed to control the mechanical system's motion within the DECY-13 cyclotron's magnetic field mapping system in both radial and angular directions, and the mapping data can be stored. (author)
001^ID2500042
008^S54/01/I/M/U
009^M
100^Linandia, Ismi Putri
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of a computer usage monitoring system based on Arduino and Fuzzy logic
230^Rancang bangun sistem monitoring penggunaan komputer berbasis Arduino dan logika Fuzzy
300^INIS-ID--0101
403^2023
500^82 p.
600^(IN)
610^29 refs.; 38 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; COMPUTERS; FUZZY LOGIC; RADIATION MONITORING; RADIATION SYNDROME; PROGRAMMING; SENSORS; EYES; HEALTH HAZARDS; RADIATION PROTECTION
009^X/EN
860^Computer usage can cause a variety of diseases, such a myopy, headache, neck pain, and backache. This can certainly be prevented if the eye health of computer users can be monitored properly. Computer Vision Syndrome (CVS) is a complex eye and vision complaint experienced when using a computer. Then built a warning system using Fuzzy logic is for one of the solutions. Fuzzy logic with Sugeno method as the core of the program for processing information. With input in the form of ping sensor for determine the distance from the user to the laptop/computer screen, the BH1750 sensor to monitor the light in the surrounding area and the millis #Greek Capital Letter Omicron# function on Arduino for input duration of using the laptop/computer, using the Arduino Uno as a microcontroller. The warning system is in the form of buzzer which will remind the user if the distance, light and duration have exceeded the safe limit determined by the system. Monitoring result can be seen directly on the serial monitor or using a data streamer on Microsoft Excel so that they can be stored and uses as evaluation material. This study produced a warning system that is useful in monitoring eye health for the prevention of CVS with a deviation standard value is 0.000748 - 0.0378. (author)
001^ID2500043
008^S43/01/I/M/U
009^M
100^Khairunisa, Jihan
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Software development to estimate beam current and irradiation time of EBM Arjuna 1.0 base on interface LabVIEW
230^Pembuatan aplikasi prediksi arus berkas dan waktu iradiasi MBE Arjuna 1.0 berbasis interface labVIEW
300^INIS-ID--0102
403^2023
500^85 p.
600^(IN)
610^27 refs.; 32 figs.; 20 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^PROGRAMMING; BEAMS; IRRADIATION; ELECTRON BEAM MACHINING; INTERFACES; LABORATORY SYSTEM; ELECTRON BEAMS; RADIATION DOSES; NUCLEAR OPERATORS; ABSORBED RADIATION DOSES; DOSEMETERS
009^X/EN
860^Currently the Electron Beam Machine (MBE) owned by PRTA - BRIN Yogyakarta is the Arjuna 1.0 MBE with energy specifications and electron beam currents of 350 keV/10mA. This Electron Beam Machine (MBE) can be used for various purposes, so it requires a varying amount of absorbed dose. If the amount of absorbed radiation dose is well controlled, the quality of the irradiation product produced can meet the needs. The problem currently faced is that the operator must estimate the irradiation time and the amount of beam current needed before carrying out the MBE Arjuna 1.0 irradiation process, while the predicted value is currently calculated manually and there is often a mismatch between the absorbed dose and the requested dose. So in this study an application (software) was created that is capable of displaying output data in the form of beam flow prediction values, sample irradiation time predictions, absorbed dose prediction and dose rate automatically for the Arjuna 1.0 Electron File Machine (MBE). The input data used includes the request dose, the input beam current of the device, the initial energy, and the sample distance. The output data is displayed in the form of a LabVIEW Human Machine Interface (HMI) to make it easier for operators to see the results of their predicted output data. Then the resulting output value is tested for percentage galat validation with the value on the Cellulose Tri Acetate (CTA) dosimeter recorded in the logbook. The percentage galat test results for predicted current, predicted irradiation time and predicted absorbed dose were respectively 5.303 %; 5.863 %; and 6.148 % for the deviation found in the MBE tool #+-# 20 % which means that the results of the test value for the application made are still below the tolerance limit for tool galat deviation so that the application can be used. After that, the value displayed on the HMI is connected to the database using MySQL via the local server. (author)
001^ID2500044
008^S42/01/I/M/U
009^M
100^Farhan, Muhammad Rizky
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Sentiment analysis on Twitter social media regarding nuclear using text mining method
230^Analisis sentimen pada media sosial Twitter terhadap nuklir menggunakan metode text mining
300^INIS-ID--0103
403^2023
500^48 p.
600^(IN)
610^23 refs.; 19 figs.; 8 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SOCIAL IMPACT; NUCLEAR ENGINEERING; COMPUTER NETWORKS; DATA; SIMULATION; ALGORITHMS; LEARNING; MAN-MACHINE SYSTEMS; DECISION TREE ANALYSIS
009^X/EN
860^Sentiment analysis is a crucial process in analyzing digital text to uncover hidden messages in emotional dimensions, such as positive, negative, or neutral. This research employs Text Mining method and focuses on social media Twitter posts with the keyword #Double Prime#nuclear#Double Prime# to support the analysis. Twitter data is processed using the RapidMiner application, which enables Machine Learning modeling. In this study, the implementation of two Machine Learning algorithms, namely Naive Bayes Classifier and Decision Tree, is conducted to construct a sentiment model. This step aims to classify posts based on the contained sentiment, whether positive, negative, or neutral. In this process, accuracy is measured for each algorithm in identifying sentiment. This research demonstrates that the highest classification of sentiment is neutral, followed by positive and negative. The accuracy results reveal that Na#Latin Small Letter I With Diaeresis#ve Bayes outperforms Decision Tree algorithm. In terms of accuracy, Na#Latin Small Letter I With Diaeresis#ve Bayes displays a percentage of 51.15 %, while Decision Tree achieves 51.79 %. Through this study, it can be concluded that sentiment regarding nuclear topics on Twitter is a widely discussed subject, leaning more towards neutral sentiment. (author)
001^ID2500045
008^S62/01/I/M/U
009^M
100^Amalia, Mariska
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Segmentation of kidney in CT images using Thresholding Otsu, Multilevel Thresholding Otsu, Active Contour, and Watershed methods
230^Segmentasi citra CT ginjal menggunakan metode Thresholding Otsu, Multilevel Thresholding Otsu, Active Contour, dan Watershed
300^INIS-ID--0104
403^2023
500^113 p.
600^(IN)
610^40 refs.; 18 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^KIDNEYS; IMAGES; CAT SCANNING; WATERSHEDS; IMAGE PROCESSING; CALCULI; CYSTS; PROBABILITY; CALCULATION METHODS
009^X/EN
860^In this research, one of the stages in image processing is carried out which is called image segmentation. The purpose of image segmentation is to identify and separate the objects in the image or divide the image into several parts. This study focuses on segmenting CT images of the kidneys with the classification of Cyst and Stone disease, as well as Normal kidneys using four segmentation methods to find which method is best, namely the Thresholding Otsu Method, Multilevel Thresholding Otsu, Active Contour, and Watershed. Furthermore, the results of image segmentation will be tested by calculating the Miclassified Area Mutual Overlap (M_M_O) value from the overlapping of manual segmentation image results which is carried out by marking areas suspected of damaged tissue using Adobe Photoshop software and automatic segmentation with the four methods used in this study. A good M_M_O value is above 50 %. The results of the best segmentation method for kidney images is Thresholding Otsu with the highest probability of 0.37. (author)
001^ID2500046
008^S60/01/I/M/U
009^M
100^Malika, Mishael Ghani
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Identification of chili plant varieties using Deep Learning and the effect of Masking use on model performance
230^Identifikasi varietas tanaman cabai menggunakan Deep Learning dan pengaruh penggunaan Masking terhadap performa model
300^INIS-ID--0105
403^2023
500^98 p.
600^(IN)
610^24 refs.; 38 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^FOOD; PLANTS; GAMMA RADIATION; IRRADIATION; MUTATIONS; SEEDS; MASKING; VEGETABLES; PERFORMANCE
009^X/EN
860^Red Chili (Capsicum annuum L) is one of the most consumed vegetable commodities by the Indonesian society. The high consumption and increasing market demand have driven producers to provide high-quality plant seeds. The current process of chili plant identification is still conducted manually by observing the morphology of the leaves and requires the assistance of experts. To expedite the identification process, a Deep Convolutional Neural Network (DCNN) is employed, which is a deep learning method designed to process two-dimensional data to accomplish identification tasks in smart farming. This research establishes a deep learning-based identification system using four models, namely AlexNet, Inception-v3, DenseNet, and VGG16, and investigates the impact of using masking on model performance for 19 varieties of chili. Three out of the four models exhibit superior results without the use of masking, while the application of masking significantly enhances the accuracy of the AlexNet model by 29 % compared to the dataset without masking. (author)
001^ID2500047
008^S46/01/I/M/U
009^M
100^Sriwa, Muh. Suhalmin
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Characterization of HPGe detector ortec GEM-S5020 with Monte Carlo simulation - GEANT4
230^Karakterisasi detektor HPGe ortec GEM-S5020 dengan simulasi monte carlo - GEANT4
300^INIS-ID--0106
403^2023
500^65 p.
600^(IN)
610^21 refs.; 18 figs.; 8 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^GAMMA RADIATION; HIGH-PURITY GE DETECTORS; MONTE CARLO METHOD; SIMULATION; CALCULATION METHODS; GE SEMICONDUCTOR DETECTORS; SEMICONDUCTOR DETECTORS; MEASURING INSTRUMENTS; RADIATION DETECTORS; RADIATIONS
009^X/EN
860^The decay of radionuclides emitting gamma energy is important in many experiments and studies. But on the other hand, a lot of equipment is needed in each experiment, so to determine the radiation characteristics and response from alone measurements requires quite expensive costs. To avoid this limitation, computer simulations can be used to estimate the experimental radiation and response characteristics using the Monte Carlo simulation software - GEANT4 to determine the response of a gamma spectroscopy detector. This research uses GEANT4 software to determine Full Energy Peak Efficiency, Energy Calibration, and Energy Resolution of HPGe Detectors with experimental data. The radionuclide sources used were Cs-137, Co-60, Co-57, Mn-54, Cd-109, Ba-133, Zn- 65, and Na-22 with different measurement distances of 8 cm, 10 cm, and 12 cm of the detector cover layer. (author)
001^ID2500048
008^S61/01/I/M/U
009^M
100^R, Muh Khaidir
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and measurement of MBE dose rate based on web application using Flask Python
230^Rancang bangun dan pengukuran laju dosis MBE berbasis web application menggunakan Flask Python
300^INIS-ID--0107
403^2023
500^48 p.
600^(IN)
610^33 refs.; 21 figs.; 1 tab.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; DOSES; DOSE RATES; WEBSITES; PROGRAMMING; ELECTRON BEAM MACHINING; IRRADIATION; RADIATION DOSES; RADIATION DOSE RATE RANGES; SIMULATION
009^X/EN
860^An electron beam machine is a prominent application of nuclear technology, commonly utilized to perform irradiation on various types of materials. This irradiation process aims to enhance the quality of the materials. Examples of irradiation applications include improving the properties of tire rubber, enhancing the production of superior electrical cables, and treating food items. In Indonesia, a electron beam machine is located at the Accelerator Technology Research Center within the National Research and Innovation Agency (PRTA-BRIN) in Yogyakarta. This machine is specified with an electron beam energy of 350 keV and a current of 10 mA. The radiation dose rate on a material is crucially important to assess its quality. Consequently, there is a need for a publicly accessible application to calculate the radiation dose rate. In this research, a web-based application was developed using the Flask Python framework. This application empowers users to easily calculate radiation dose rates. Based on simulation results, the calculation model on the website closely approximated the measurement outcomes, with a deviation value of 8.01 %. Measurement discrepancies can be influenced by various factors, including background radiation, instrument calibration factors, and the efficiency of tungsten. (author)
001^ID2500049
008^S46/01/I/M/U
009^M
100^Valentino, Muhammad Rizki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of a Smart Water meter system with LC sensors using STM32L05
230^Rancang bangun sistem Smart Water meter dengan sensor LC menggunakan STM32L05
300^INIS-ID--0108
403^2023
500^60 p.
600^(IN)
610^35 refs.; 35 figs.; 3 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WATER; SENSORS; DRINKING WATER; METERS; DIGITIZERS; CONVENTIONAL WARFARE; OSCILLATIONS; SIGNALS
009^X/EN
860^The availability of sufficient water is crucial for human survival. In Indonesia, PDAM is one of the providers of drinking water for the public. However, PDAM still faces problems in providing water, one of which is the issue of unbilled water consumption or NRW. NRW often occurs due to various factors, one of which is errors in water meters, such as incorrect reading or inaccuracies in water meter of customers. The purpose of this research is to develop a prototype of a smart water meter system using an LC Sensor and leveraging the STM32L05 microcontroller to digitize conventional water meters. The hardware design involves the integration of the LC sensor circuit, LoRa Ra-01H module, and STM32L05 microcontroller based on datasheets and relevant references. The program design is carried out using STM32CUBE IDE, enabling the microcontroller functions to activate and count the oscillation signals. The test results demonstrate that the LC sensor successfully generates oscillation signals, and subsequently, the reading outcomes are displayed through UART communication. (author)
001^ID2500050
008^S21/01/I/M/U
009^M
100^Akbar, Muhammad Salino
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of PLC-Based acquisition for Kartini reactor operational parameters
230^Perencanaan dan pengembangan akuisisi parameter operasi reaktor Kartini berbasis PLC
300^INIS-ID--0109
403^2023
500^146 p.
600^(IN)
610^22 refs.; 76 figs.; 19 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; REACTORS; DATA ACQUISITION; REACTOR OPERATION; KARTINI-PPNY REACTOR; MATHEMATICAL LOGIC; NATURAL ANALOGUE; ELECTRIC POTENTIAL; SIGNALS; MONITORING; RADIATION MONITORING
009^X/EN
860^Development of data acquisition system for operation of the Kartini reactor was carried out by using programable-logic controller (PLC). The development is based on the recommendation of an expert team of the International Atomic Energy Agency which justifies that the previous data acquisition system of the reactor operation has been considered obsolete. This research aims to follow up the recommendation by using a recent technology of PLC as the basis of the system. The parameter acquisition method was done by acquiring the analogue and digital voltage signals by the PLC and processing them into values accordingly. Analogue parameters: linear power, logarithmic power percent, period, and three control bars. Digital parameters: trigger trip signals. Parameter values are visually displayed using LabVIEW. The test method was comparing the obtained values to the current monitoring subsystem. Test results: linear power error is 0.09 %; period error is 0.8 %; and error of the three control rods is below 1 %. All digital signal test results successfully show appropriate trip conditions when active. The conclusion of this study is successful in making a design of the Kartini Reactor process parameter acquisition system with small relative errors to the existing system. (author)
001^ID2500051
008^S46/01/I/M/U
009^M
100^Kirana, Nabella Syahda
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Web-Based image dataset management and auto machine learning application development
230^Pengembangan aplikasi image dataset management dan auto machine learning berbasis web
300^INIS-ID--0110
403^2023
500^108 p.
600^(IN)
610^39 refs.; 130 figs.; 15 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^WEBSITES; PROGRAMMING; IMAGES; IMAGE PROCESSING; MACHINE TRANSLATIONS; ARTIFICIAL INTELLIGENCE; LEARNING; SIMULATION; PLANTS
810^
009^X/EN
860^In the modern era, computer vision research has developed significantly. The use of modern technology-based tools, where all processes run using the internet and the emergence of intelligence systems controlled by data through machine learning and AI (Artificial Intelligence) technology. One of the fields that uses this technology is agriculture, by utilizing plant morphology, one of which is leaves. To get good model performance, the dataset must also be well organized before the data training process is carried out. In its development, deep learning models that are deployed in browsers have been introduced to develop machine learning. Therefore, this study developed a web-based system that can manage datasets to carry out data training processes with several architectures, namely AlexNet, Inception-v3, DenseNet121, and VGG16, for chili leaf image datasets. This study uses the chili leaf dataset obtained from the PRSDI - BRIN Bandung research for the data training process. The method used in web development is the agile SDLC. The framework used for web development is Laravel. This website is run on a local server, namely XAMPP and the data is stored using MySQL. The leaf dataset displayed on the website is the result of retrieving data from S3 Compatible Storage. Data processing by the user is done by changing the label if there is an error in the image data label. This website displays the results of model predictions from the data training process in the form of graphs of accuracy and graphs of loss to the user. (author)
001^ID2500052
008^S46/01/I/M/U
009^M
100^Syawaludin, Qinthara Fatha
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Prototipe design of Radiation Portal Monitor (RPM) pedestrian based on raspberry PI
230^Perancangan prototipe Radiation Portal Monitor (RPM) pedestrian berbasis Raspberry PI
300^INIS-ID--0111
403^2023
500^104 p.
600^(IN)
610^17 refs.; 63 figs.; 37 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; RADIATION MONITORING; PORTAL SYSTEM; MONITORING; RADIATION DETECTION; ALGORITHMS; PROGRAMMING LANGUAGES; FACE; DISTANCE
009^X/EN
860^Radiation Portal Monitor (RPM) is a radiation detection device in the form of two pillars facing each other at a certain distance. The purpose of this study is to design devices both software and hardware using the Raspberry Pi. From the results of this study the Raspberry Pi succeeded in utilizing the count value obtained from the microcontroller to turn on the alarm which is used as an indicator of the threshold value. Apart from the alarm, there are other components such as PIR sensors, LEDs, and also the INA219 sensor as supporting components of the RPM system that is made. In utilizing count values, the authors designed an algorithm using the python programming language. The results of this study indicate that the algorithm created to activate the alarm from the count value obtained from Arduino has been successfully carried out. (author)
001^ID2500053
008^S43/01/I/M/U
009^M
100^Pratama, Rafi Bagas
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Operation and control system simulation design on PLC-Based DECY-13 cyclotron
230^Rancangan simulasi sistem operasi dan kendali pada siklotron DECY-13 berbasis PLC
300^INIS-ID--0112
403^2023
500^46 p.
600^(IN)
610^19 refs.; 18 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^CONTROL SYSTEMS; SIMULATION; DESIGN; CYCLOTRONS; NUCLEAR MEDICINE; RADIOISOTOPES; TOMOGRAPHY; NEOPLASMS; MAGNETIC FIELDS; SAFETY; CYCLONE CYCLOTRON
009^X/EN
860^A cyclotron is one of the tools used in the medical field, one of which is to produce radioisotopes, which are used to diagnose cancer in the human body using Positron Emission Tomography (PET). Development of Experimental Cyclotron in Yogyakarta - 13 MeV (DECY-13) is a cyclotron being developed by the Accelerator Technology Research Center (PRTA). In a cyclotron there are several main component systems needed to operate, including: a cooling system, a vacuum system, a magnetic system, an ion source, and a radio frequency (RF) system. These components are not yet integrated. When the tool is operating, the operator is still monitoring manually by approaching each component. In this case, it is necessary to integrate the constituent components of the DECY-13 cyclotron into a single control system. The integration process has been simulated using the F2424 PLC as a controller using the input keyboard, i-TRILOGI and LabVIEW software. Each system has an input value that must be met to run the program, for a vacuum value with a high vacuum level of 10#Up Arrowhead#(-6)torr, for a magnetic system value is 1.2 Tesla, for a radiofrequency system with a frequency value of 77.7 MHz, a power value of 20 kw, and a phase value of 0"o, for an ion source with a gas current value of 10 sccm and a plasma current value of 250 mA, for a target system with a beam current value of 20#Greek Small Letter Mu#A and position 0. In the research that has been done, the results are manual program simulation and automatic program simulation, the research has been carried out in accordance with the research objectives and it can be concluded that with this research the operator does not need to enter the operating room during operation, this is to increase safety in cyclone operation because the voltage released is quite large. (author)
001^ID2500054
008^S54/01/I/M/U
009^M
100^Rajasa, Rangga
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Monitoring system design of photovoltaic power plant using Arduino and Grafana
230^Rancang bangun sistem monitoring PLTS fotovoltaik menggunakan Arduino dan Grafana
300^INIS-ID--0113
403^2023
500^66 p.
600^(IN)
610^14 refs.; 32 figs.; 9 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^MONITORING; DESIGN; PHOTOVOLTAIC EFFECT; PHOTOVOLTAIC POWER PLANTS; SOLAR POWER PLANTS; DATA ANALYSIS; REFRIGERATORS; STATISTICAL DATA; NUMERICAL DATA
009^X/EN
860^Indonesia is a country located on the equator, this makes Indonesia get abundant sunshine most of the year. Therefore, Indonesia has the potential for solar energy that can be utilized and developed, one of which is the Photovoltaic (PV) Power Plant. Monitoring the performance of PV is important to ensure that PV operates at optimal levels, and to identify potential problems before they occur. This research designs and builds a monitoring system for solar power plants. The monitored parameters are solar panel voltage, solar panel current, solar panel power, load voltage, load current, load power, solar irradiance, daily energy production, daily energy consumption, and electricity cost savings. Parameter measurement will be carried out using sensors, namely power meters, and pyranometer. These sensors will be connected to the Arduino Uno microcontroller. Data transmission from Arduino Uno to the computer will be done using TCP/IP communication via ethernet cable. Furthermore, the data will be sent to the computer to be stored in a local database which will then be displayed on the GUI (graphical user interface). The database that used is the MySQL database, locally stored on a computer, and the Grafana Dashboard used as a GUI to display data recorded. (author)
001^ID2500055
008^S21/01/I/M/U
009^M
100^Prawoto, Rankai Rasya
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Watchdog design for Kartini's Reactor protection system upgrade
230^Rancang bangun Watchdog untuk peningkatan sistem proteksi Reaktor Kartini
300^INIS-ID--0114
403^2023
500^72 p.
600^(IN)
610^21 refs.; 41 figs.; 13 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; KARTINI-PPNY REACTOR; SAFETY; RADIATION PROTECTION; ELDERLY PEOPLE; REACTOR DECOMMISSIONING; MONITORING; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; COMPUTER CODES
009^X/EN
860^The aging problem and the scarcity of components on the control computer at the Kartini reactor are the main factors for the revitalization process. With these problems, some functions in the Kartini reactor are not running according to design, and one of them is the watchdog system of the control computer (slave PC). The watchdog system plays a role in monitoring the failure of the control computer if there is a hang during the operation process. If there is a hang on the computer, the watchdog system will actuate the reactor protection system in the form of a reset system and TRIP (reactor shutdown). However, the system is only able to actuate the reset system while the TRIP system is run manually. In this study, a watchdog system was designed to monitor the performance of PLC and LabVIEW-based control computers. Testing is based on the output signal specifications of the control computer used and the quality of the output signal. Based on the test results, it can be seen that the system is able to read the hang and generate a delay signal to actuate SCRAM. In addition, the prototype watchdog timer is more ideal if used in low-frequency supervisory signals compared to existing circuits. (author)
001^ID2500056
008^S46/01/I/M/U
009^M
100^Hidayat, Ryan
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Performance analysis of convolutional neural network - support vector machine method in liveness detection
230^Analisis performa metode convolutional neural network - support vector machine dalam liveness detection
300^INIS-ID--0115
403^2023
500^59 p.
600^(IN)
610^14 refs.; 30 figs.; 4 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^PERFORMANCE; NEURAL NETWORKS; VECTOR PROCESSING; MACHINERY; BIOMETRIC AUTHENTICATION; NUCLEAR WEAPONS; DETECTION; FACE; KERNELS
009^X/EN
860^Currently, biometric systems are capable of identifying individuals but are not able to prevent various types of fraudulent attacks. Therefore, the presence of liveness detection is needed, which can differentiate between live and fake faces. The aim of this research is to analyze the performance of methods in liveness detection. This study employs facial samples that will be trained and tested using Convolutional Neural Network-Support Vector Machine (CNN-SVM), along with varying the existing parameters. The changes in parameters will be analyzed to determine how optimally these parameters are utilized to train and test the model with the available dataset. The obtained results from the testing range between 48 % and 53 %. By altering parameters such as CNN layers, kernels, and the regularization employed by SVM, the accuracy of each parameter modification can be identified. The most optimal parameter configuration is the use of a linear kernel and regularization of 1000, along with CNN layers starting with a filter size of 32. (author)
001^ID2500057
008^S46/01/I/M/U
009^M
100^Wibowo, Zahra Zahira
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of radiology and nuclear medicine laboratory management information system with REST API implementation based on codeigniter framework
230^Rancang bangun aplikasi sistem informasi manajemen laboratorium radiologi dan kedokteran nuklir dengan implementasi REST-API berbasis codeigniter framework
300^INIS-ID--0116
403^2023
500^165 p.
600^(IN)
610^50 refs.; 56 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; RADIOLOGY; NUCLEAR MEDICINE; INFORMATION SYSTEMS; DATA; DATA PROCESSING; WEBSITES; PROGRAMMING LANGUAGES; ENRICHMENT
009^X/EN
860^Efforts to improve educational services at the Radiology and Nuclear Medicine Laboratory of the Nuclear Technology Polytechnic of Indonesia include providing easier access to laboratory information for both users and laboratory administrators. Currently, the entire managerial activities and data archiving processes are not optimal due to the continued use of data processing applications, which makes it difficult for administrators to manage laboratory needs and hinders users from obtaining the necessary information. To address this issue, a Radiology and Nuclear Medicine Laboratory Management Information System with a Web-Based Interoperability System has been developed, aiming to facilitate information distribution and support laboratory management processes. The application has been built using PHP programming language with the Codeigniter framework, HTML, CSS, and is equipped with a MySQL database management system. Additionally, the application has been supported with an interoperability system that enables data exchange with other applications through provided APIs. It has successfully utilized radioisotope level data provided by the International Atomic Energy Agency (IAEA) API. Functional testing using the Black Box method and API testing with Postman have been conducted on the application, and both test results are considered to have passed and aligned with the test criteria. With the implementation of this application, it is expected to contribute to the enhancement of educational service quality by optimizing data and information management and providing ease of access. Moreover, the application's interoperability is expected to enrich laboratory information and facilitate integration with other relevant applications. (author)
001^ID2500058
008^S62/01/I/M/U
009^M
100^Wachidah, Zakia Nur
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Control system design of test sample table position for CT X-ray digital radiography prototype at PRTDRAN-BRIN Serpong as radiation safety optimization
230^Rancang bangun sistem pengendali posisi meja sampel uji untuk prototipe radiografi digital CT sinar-X di PRTDRAN-BRIN Serpong sebagai optimisasi keselamatan radiasi
300^INIS-ID--0117
403^2023
500^83 p.
600^(IN)
610^25 refs.; 39 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^CONTROL SYSTEMS; DESIGN; DATA; CAT SCANNING; GAMMA RADIATION; X-RAY RADIOGRAPHY; IMAGES; DETECTION; SENSORS
009^X/EN
860^Digital Radiography is a form of X-ray imaging where the X-ray detection sensors used are digital instead of conventional radiographic film. In the industrial field, digital radiography has many uses, one of which is to detect or test damage or defects in an invisible product. In this research, a test sample position control system was designed for the X-ray CT Digital Radiography Prototype at PRTDRAN ORTN BRIN Serpong for the z-axis motion direction. The purpose of this research is to design a motion control system program from the test sample table component in the z-axis direction on the CT X-ray digital radiography prototype at PRTDRAN ORTN BRIN Serpong, then make a stepper motor circuit with an Arduino Uno microcontroller as a control system for the z-axis direction test sample table movement on the CT X-ray digital radiography prototype at PRTDRAN ORTN BRIN Serpong, and make a prototype development module based on the design of the z-axis direction test sample table movement control system on the CT X-ray digital radiography prototype at PRTDRAN ORTN BRIN Serpong. The results of this research have been able to move the test sample table on the CT X-ray digital radiography prototype at PRTDRAN ORTN BRIN Serpong with a maximum load of 30 Kg, as well as a form of further development for the control system of the test sample table components on the CT X-ray digital radiography prototype at PRTDRAN ORTN BRIN Serpong. (author)
001^ID2500059
008^S12/01/I/M/U
009^M
100^Zulfiyandi
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The needs assessment on the application of risk management and risk analysis to maintenance activities in radioactive waste management installation
230^Kajian kebutuhan penerapan manajemen risiko dan analisis risiko dalam kegiatan perawatan instalasi pengelolaan limbah radioaktif
300^INIS-ID--0118
403^2023
500^76 p.
600^(IN)
610^16 refs.; 8 figs.; 17 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^CHARGES; RISK ASSESSMENT; RADIOACTIVE WASTE MANAGEMENT; WASTE MANAGEMENT; NUCLEAR FACILITIES; FAULT TREE ANALYSIS; REACTOR PROTECTION SYSTEMS; LIQUID WASTES; DECISION MAKING
009^X/EN
860^From the maintenance activities carried out so far at IPLR, it has not been seen that Risk Management has been implemented properly so that there are various obstacles in the implementation of maintenance activities carried out by the implementers of activities. Obstacles in the implementation of activities can be caused by various things, so that the causative factors must be controlled so that the possibility of failure or obstacles in the implementation of activities can be reduced as little as possible and do not have a wider impact on failures in the service processes provided by IPLR. The process of determining the cause of risk is carried out using the Fault Tree Analysis method which is then described in the Boolean Algebra equation to obtain a Minimal Cut Set, where the Minimal Cut Set obtained is assumed to be the main cause of the risk. By entering the Minimum Cut Set into the Risk Management Working Paper and by considering the Probability Level Criteria and Impact Level Criteria, a Risk Distribution Map and a Residual Risk Expectation Map will be obtained. From Risk Analysis for Detection System Maintenance in Physical Protection Systems obtained 13 Minimum Cut Sets with a chance of 8 events a year, and for Liquid Radioactive Waste Management Services obtained 9 Minimum Cut Sets with a chance of 5 events a year, and for Work Area Radiation Exposure Monitoring Services obtained 4 Minimum Cut Sets with a chance of 1 event a year. By paying further attention to the results of the risk analysis that has been carried out, it can be known the human error factor, which is a factor that always exists in every implementation of activities so that this must be controlled as well as possible. In addition, the procurement factor of goods/services is also very important to pay attention to, especially for the implementation of maintenance activities, and the availability of supporting data is one of the important factors as a basis for decision making by stakeholders. (author)
001^ID2500060
008^S36/01/I/M/U
009^M
100^Rohman, Abidur
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effect of gas mixture N_2:Ar in the sputtering process on the surface properties of N/TiN bi-layers on stainless steel 316L
230^Pengaruh campuran gas n_2:Ar pada proses sputtering terhadap sifat permukaan lapisan bi-layer N/TiN pada baja tahan karat stainless steel 316L
300^INIS-ID--0119
403^2023
500^105 p.
600^(IN)
610^29 refs.; 28 figs.; 16 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^GASES; MIXTURES; SPUTTERING; SURFACE PROPERTIES; STAINLESS STEELS; IMPLANTS; RAW MATERIALS; NITRIDATION
009^X/EN
860^Stainless steel 316L is widely used as an implant biomaterial due to its easy availability. However, this 316L stainless steel biomaterial has the disadvantage that it is not resistant to wear and low hardness so that it cannot be used for a long period of time. In this study, the quality of a material was improved by surface treatment on the surface of SS 316L using DC sputtering technique which had previously been carried out plasma nitriding process on the surface of SS 316L sample. Plasma nitriding is carried out for 4 hours with a pressure of 1.6 mbar and a temperature of 400 #Degree Sign#C, the sputtering process uses voltage, current, pressure and time at constant conditions of 5 kV, 10 mA, order 10"-"2 mbar and 2 hours and a mixture of Ar: N_2 gas which is 60: 40, 70: 30, and 80: 20. The process resulted in a bi-layer N/TiN coating. The results of the coating process were carried out Vickers hardness testing with a load of 10 gf to get the highest hardness when sputtering with a gas mixture of 70 %Ar and 30 %N_2 of 1051.86 VHN with an increase of 4.38 times from the raw material hardness of 219.48 HVN. The wear test was carried out with a decrease in the wear rate results (more wear-resistant) on the sample when sputtering with a gas mixture of 70 %Ar and 30 %N_2 of 15.24 x 10"-"6 mm"2/kg and the raw material wear rate of 28.94 x 10"6 mm"2/kg. The wettability test obtained the most optimum surface contact angle value in the sputtering process with a gas mixture of 70 %Ar and 30 %N_2 with a surface contact angle value of 54.5#Degree Sign#. New compounds were obtained from XRD testing on samples during plasma nitriding, namely Fe_3N, Cr_2N and sputtering (N/TiN bi-layer results), namely Fe_2N, Fe_3N, CrN, Cr_2N, Ti and TiN. The formation of TiN layer on 316L stainless steel specimens as evidenced by the appearance of TiN phase peaks 111, 113, 311. Based on the analysis results, the N/TiN bi-layer layer is formed consisting of metal nitride layers (FeN and CrN) from the nitriding process and TiN layer from the sputtering process, this layer can improve the surface quality of SS 316L, especially hardness and wear resistance. (author)
001^ID2500061
008^S62/01/I/M/U
009^M
100^Fauzi, Ahmad
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of the use of X-ray collimator filters on the quality of radiography images with digital radiography
230^Analisis penggunaan filter colimator sinar-X terhadap kualitas citra radiografi dengan digital radiography
300^INIS-ID--0120
403^2023
500^51 p.
600^(IN)
610^20 refs.; 29 figs.; 3 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^GAMMA RADIATION; COLLIMATORS; BIOMEDICAL RADIOGRAPHY; X-RAY RADIOGRAPHY; IMAGES; DIGITAL SYSTEMS; FILTERS; THICKNESS; COMPUTERIZED TOMOGRAPHY
009^X/EN
860^Analysis of the Use of X-ray Collimator Filters on Radiographic Image Quality with Digital Radiography. A filter is a material designed to selectively absorb X-ray beams. The inherent filter is not enough to absorb low radiation, so an additional filter is needed. This research will produce an analysis of variations in the type of collimator filter material and an analysis of variations in the thickness of the collimator filter material on the quality of radiographic images. This research uses Computed Radiography and with an X-ray tube voltage of 140 kV with a time of 4 minutes for each irradiation. Comparison of radiographic image quality was carried out by observing the contrast of radiographic images by varying the type of material (aluminum, copper, brass) and filter thickness (0.5 mm, 1.0 mm, 1.5 mm, and 2 mm). The results of this study obtained the average maximum contrast always increases in each type of filter and filters with brass material thickness of 2 mm produce average maximum contrast of 22657 and the highest compared to other materials. (author)
001^ID2500062
008^S46/01/I/M/U
009^M
100^Naufal, Akmal
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Optimization 3-phase electrical load balance at the Nuclear Polytechnic Campus - BRIN by ETAP software
230^Optimasi keseimbangan beban listrik 3 fasa pada kampus Poltek Nuklir - BRIN menggunakan software ETAP
300^INIS-ID--0121
403^2023
500^109 p.
600^(IN)
610^14 refs.; 28 figs.; 37 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^OPTIMIZATION; ELECTRICITY; PROGRAMMING; POWER PLANTS; BALANCES; LOAD ANALYSIS; SIMULATION; TRANSFORMERS; POWER SYSTEMS
009^X/EN
860^In the distribution of electricity from the power plant to the Nuclear Polytechnic - BRIN there is always an imbalance in the load current, which is obtained from the use of electrical energy on a single phase that is uneven and results in a load imbalance that has an impact on the supply of electricity. From these problems, this research aims to find out the overall condition of an electricity network on the Nuclear Polytechnic - BRIN campus. Then balanced load optimization is carried out so that load imbalance can be minimized. The method used is to measure and record each piece of equipment connected to the distribution panel and optimize the equipment load by moving the load from one phase to another if there is a load imbalance. In this study, ETAP software is used to simulate electricity in full load conditions and see the currents that appear when in unbalanced conditions and simulate balanced load optimization. From the results of the study there was a load imbalance in the LVMDP panel at full load of 30 % and after optimizing the balanced load the resulting load balance was 9 %, in accordance with the requirements of IEEE 466-1995. While the amount of power loss at full load is 79.9 kW of active power and 119 kvar of reactive power and transformer loading shows at 268 %. (author)
001^ID2500063
008^S42/01/I/M/U
009^M
100^Pattin, Aldo Gallant Jandu
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of a website-based risk based inspection calculating system for industrial pipelines
230^Rancang bangun sistem penghitung risk based inspection pada pipa industri berbasis website
300^INIS-ID--0122
403^2023
500^50 p.
600^(IN)
610^19 refs.; 13 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WEBSITES; RISK ASSESSMENT; INSPECTION; INDUSTRY; PIPELINES; CALCULATION METHODS; PIPES
009^X/EN
860^This research is motivated by the calculation of the Risk Based Inspection matrix values for pipes using the manual method. In manual calculations, errors often occur in processing data. The data on the pipe is calculated manually, where in the process of calculating the data must require high accuracy. In this case, it is necessary to have a matrix value calculation system on the pipe automatically. The website is used as a medium for calculating matrix values that are easy to use. In making websites, python and django are the basic programming languages. The purpose of this research is to create and implement a risk-based inspection matrix value calculation system for website-based pipes. In this study, 2 test methods were used, namely Functionality Test and Performance Test. Functionality test uses the Black Box Testing method, with the aim of knowing whether the functions in the program provide the appropriate output. The results shown in the study can be seen by the system in testing according to the system diagram design and giving the appropriate response. The performance test is carried out by checking through the speed load test on the Google Chrome tool feature. In speed testing, the login page has the longest speed of 2290 ms, and the input cof page has the shortest speed of 339 ms. And the results are obtained according to an average speed of 1595.9 ms on the Chrome browser and Opera Mini. If the conversion speed is 1.5 seconds, it is certain that the speed obtained is very good. Based on the results of the research that has been done, it can be concluded that programming has been successfully implemented in a website-based risk matrix calculating system on industrial pipes. (author)
001^ID2500064
008^S62/01/I/M/U
009^M
100^Rumae, Alpriliancy
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Comparative analysis of direct radiography and computed radiography image quality on brass specimens
230^Analisis perbandingan kualitas citra direct radiography dan computed radiography pada spesimen kuningan
300^INIS-ID--0123
403^2023
500^97 p.
600^(IN)
610^32 refs.; 68 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^COMPARATIVE EVALUATIONS; X-RAY RADIOGRAPHY; COMPUTERIZED TOMOGRAPHY; IMAGES; BRASS; METALS; THICKNESS; IRRADIATION; BIOMEDICAL RADIOGRAPHY
009^X/EN
860^Brass metal is widely used in industry. However, there is currently no data on the comparison of radiographic image quality from Direct Radiography and Computed Radiography using brass specimens with varying thicknesses. Therefore, this study aims to compile reference data and selection parameters between Direct Radiography and Computed Radiography on brass materials in industry or science based on the image quality of both devices. This study was conducted by irradiating the test material in the form of step wedge-shaped brass. The exposure was done with a current of 5 mA and SFD of 930 mm. The exposure voltage (kV) used is in the range of 100-140 kV with time according to the thickness of the brass material which is equalized with the thickness of iron. The thickness of brass used is 2 mm, 3 mm, 4 mm, 5 mm, 6 mm, 7 mm, 8 mm, and 9 mm, from the calculation results of each material thickness. Digital radiography images were analyzed with Rhythm Review software for further comparison of grey values and sensitivity. The smallest grey value error is 0.043 % at brass thickness variations of 3 mm, 5 mm, and 7 mm using Direct Radiography. While the largest grey value error is 0.102 % in the brass thickness variation of 4 mm using Computed Radiography. So it is known that the deviation or grey value error in Direct Radiography is smaller than Computed Radiography. The best sensitivity value is generated in irradiation using Direct Radiography which is 1.59 % while the largest sensitivity is generated in irradiation using Computed Radiography which is 4.64 %. The results of this study found that Direct Radiography has better sensitivity than Computed Radiography. Overall, it can be concluded that Direct Radiography has better radiographic digital image quality than Computed Radiography. (author)
001^ID2500065
008^S36/01/I/M/U
009^M
100^Marta, Amelia Rahmanda Dwi
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of focal spot dimension using pinhole and multihole methods on X-ray Rigaku 250EG-S3 and Eresco 65 MF4
230^Analisis dimensi focal spot menggunakan metode pinhole dan multihole pada sinar-X Rigaku 250EG-S3 dan Eresco 65-MF4
300^INIS-ID--0124
403^2023
500^120 p.
600^(IN)
610^33 refs.; 32 figs.; 28 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DIMENSIONS; METALS; THICKNESS; X-RAY RADIOGRAPHY; FILMS; COMPUTERS; INDUSTRIAL RADIOGRAPHY; NONDESTRUCTIVE TESTING
009^X/EN
860^The X-ray tube has a focal spot component that acts as the source of the X-rays. As the X-ray machine ages, it will change the dimensions of the focal spot. The size of the focal spot dimensions greatly determines the geometric unsharpness value. One of them will affect the radiographic resolution. The purpose of this study was to find out the size of the focal spot of the Rigaku 250EG-S3 X-ray machine, whether the dimensions of the focal spot were in accordance with the specifications of the equipment or not, and the dimensions of the focal spot of the Eresco 65 MF4 X-ray machine from the use of the pinhole and multihole methods in digital radiography (radiography computer). This study obtains the best voltage using the pinhole method if the CNR is high at a voltage of 170 kV. A voltage of 170 kV is used for the FOD variation of the two methods of the Eresco 65 MF4 X-ray machine. The results of the best FOD variation of the Eresco 65 MF4 X-ray aircraft at FOD 490,5 mm resulted in a focal spot dimension of 2.75 mm x 3.05 mm for the pinhole method and 2.89 mm x 3.16 mm for the multihole method. The results of the error values of the two methods are accumulated on the Rigaku 250EG-S3 X-ray machine, resulting in a focal spot dimension of 2.36 mm x 2.26 mm for the pinhole method and 2.37 mm x 2.24 mm for the multihole method. From the multihole method, the Eresco 65 MF4 X-ray machine has a small error value, so the focal spot size of the Rigaku 250EG-S3 X-ray machine is actually found in the multihole method of 2.37 mm x 2.24 mm with changes in dimensions according to the specifications of the tool not exceeding or less than tolerance (#+-# 50 %). (author)
001^ID2500066
008^S46/01/I/M/U
009^M
100^Suhardi, Anang
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and manufacture system mechanical of automatic gamma scanner for internal structure inspection in industrial process columns
230^Rancang bangun sistem mekanik pemindai gamma otomatis untuk pemeriksaan struktur internal pada kolom proses industri
300^INIS-ID--0125
403^2023
500^131 p.
600^(IN)
610^29 refs.; 45 figs.; 17 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; MANUFACTURERS; GAMMA DETECTION; IMAGE SCANNERS; INSPECTION; MEASURING INSTRUMENTS; PETROCHEMICAL PLANTS; PERSONNEL; REACTOR OPERATORS; GAMMA RADIATION; GAMMA RADIOGRAPHY
009^X/EN
860^Gamma scanning is a nuclear inspection technique widely used to troubleshoot industrial instruments in refineries and petrochemical plants such as distillation columns, pipes, and reactors. At the time of scanning the mechanical device is manually operated by 2-3 operators simultaneously so that the number of workers and operator errors (human error) become one of the inspection problems. For that reason, the purpose of this research is to produce an automatic mechanical gamma scanner system for internal structure inspection in process columns. This research begins with the design and specification of gamma scanners for the needs of several systems that will be used. Continue with manufacturing and assembly process and then test the mechanical function of the tool with the motor. The automatic gamma scanner has been successfully made with a length of 450 mm, a width of 350 mm and a height of 220 mm and a weight of 20 kg and has produced a miniature distillation column with a diameter of 30 cm and a height of 2 meters. The tool has an average precision on the detector of 99.14 % and on the source of 99.28 % while the average accuracy on the detector is 96.99 % and on the source of 97.46 %. Gamma scanning was applied to a miniature distillation column so that this gamma scanning technique has succeeded in giving data on the internal structure of the distillation column. (author)
001^ID2500067
008^S36/01/I/M/U
009^M
100^Risa, Anugrah Muhammad
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Effect of N/WN Bi-layer coating on surface mechanical properties of AISI 1010 steel
230^Pengaruh lapisan Bi-layer N/WN terhadap sifat mekanik permukaan baja AISI 1010
300^INIS-ID--0126
403^2023
500^89 p.
600^(IN)
610^18 refs.; 12 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^LAYERS; COATINGS; SURFACES; MECHANICAL PROPERTIES; ALUMINIUM; STEELS; CARBON STEELS; WEAR RESISTANCE; SPUTTERING; RAW MATERIALS
009^X/EN
860^AISI 1010 steel is a type of carbon steel that is widely used in industry because it is easy to form, has good weldability and is easy to machining. The weakness of AISI 1010 steel is its mechanical properties including low hardness and wear resistance. This weakness can be overcome by surface treatment especially to improve the quality of the surface so as to increase the hardness and wear resistance of the surface. Surface treatment was carried out by plasma nitriding process and continued by DC sputtering to form a bi-layer N/WN layer. The plasma nitriding process was carried out at a temperature of 450 #Degree Sign#C, a pressure of 1.6 mbar and a time of 4 hours, while the DC sputtering process used a gas mixture of Ar:N_2, namely: 100 %Ar, 80 %Ar:20 %N_2, 70 %Ar:30 %N_2, and 60 %Ar:40 %N_2. The test results showed that the highest increase in hardness was obtained in the nitriding treatment and continued with sputtering with a gas mixture of 70 %Ar:30 %N_2 of 5484.12 VHN from 99.73 VHN raw material, wear rate of 8.9#Multiplication Sign#10"-"6 mm"2/kg from raw material 92.18#Multiplication Sign#10"-"6 mm"2/kg, and corrosion rate 0.14645 mm/a from raw material 3.6698 mm/a. Based on the results of the XRD test, it was shown that the N/WN bi-layer coating produced new phase/compound layers, including W, Fe_2N, Fe_3N, and Fe_4N which increased the hardness, wear resistance, and surface corrosion resistance of AISI 1010. (author)
001^ID2500068
008^S62/01/I/M/U
009^M
100^Supiyan, Arif Dwi
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The effect of imaging plate processing delay on image quality in computed radiography CRx vision
230^Pengaruh penundaan pemrosesan imaging plate terhadap kualitas image pada computed radiography CRx vision
300^INIS-ID--0127
403^2023
500^75 p.
600^(IN)
610^36 refs.; 11 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^IMAGES; NMR IMAGING; PLATES; IMAGE PROCESSING; COMPUTERIZED TOMOGRAPHY; CAT SCANNING; IRRADIATION; THICKNESS; CALCULATION METHODS
009^X/EN
860^Conditions in the field often delay the scanning process due to the distance of the inspection location from the power source or the occurrence of power outages as well as in the problematic image reader, causing the imaging plate (IP) scanning process to be delayed. As a result, this condition can cause a decrease in the quality of the radiographic image produced, so this research was conducted with the aim of obtaining data on the effect of the delay in processing the imaging plate in computed radiography on image quality. Radiographic image quality includes grey value, normalized signal to noise ratio (SNR), and normalized contrast to noise ratio (CNR). This research is a quantitative study with an experimental approach. The research sample is the result of irradiating an iron stepwedge having 13 steps with thickness variations of 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, and 14 mm using an imaging plate with a time of 0, 0.5, 1, 1.5, 2, 2.5, 3, 4, and 5 hours. Each sample was repeated three times with the aim of more accurate test results. Image pixel value and noise were measured using Rhythm Review and Rhythm RT software to determine image quality, then linear regression data analysis was performed using SPSS software. The results of research on Imaging Plate (IP) processing delays on Image quality there is an influence between the IP scanning delay time on the quality of the resulting image. Grey value decreased from 5 hours scanning delay by 58 %. The normalized SNR value decreased from 5 hour scanning delay by 26 %. The normalized CNR value decreased from scanning delay 5 hours by 11 %. (author)
001^ID2500069
008^S46/01/I/M/U
009^M
100^Rania, Aurora Azalea
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Mechanical design of portable parallel beam gamma tomography system for industrial applications
230^Rancang bangun mekanik sistem tomografi gamma portable parallel beam untuk aplikasi industri
300^INIS-ID--0128
403^2023
500^119 p.
600^(IN)
610^28 refs.; 61 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; PORTABLE EQUIPMENT; PARALLEL PROCESSING; BEAMS; TOMOGRAPHY; COMPUTERIZED TOMOGRAPHY; INDUSTRY; GEOTHERMAL POWER PLANTS; SAFETY; REACTOR SAFETY
009^X/EN
860^Several types of scaling have been observed in geothermal power plant installations as well as in the crude oil distribution process. From these cases, tomography is one of the methods that can be chosen to be a solution to the problems that occur because the application of tomography is able to access the detailed structure of any object without damage. Therefore, this research will create a mechanical design of a portable gamma parallel beam tomography system. The purpose of this research is to design a mechanical portable parallel beam gamma tomography system. This research method begins with designing a design using Autodesk Inventor software where there are three main parts, namely the translational motion part, the rotational motion part and the support and calculation. Then the manufacturing, assembly and testing process is carried out. In this study, the mechanical device has been built with a weight of #+-# 60 kg, overall length of 1650 mm #Multiplication Sign# width of 840 mm #Multiplication Sign# maximum height of 950 mm which can detect pipes with a maximum diameter of 450 mm, accuracy and precision values of translational movements of 98.49 % and 98.69 %, the value of the movement of each constant gear rotation of 5 rpm as many as 6 teeth/1 rotation and and the safety factor value for testing the mechanical strength of the aluminum profile; lead screw; open builds linear actuator; bevel gear; circular rail; open builds circular rail; spur gear; upper support frame and support legs have a value >1. So it can be seen that the tool is able to operate properly and can be useful for the industrial world. So it can be seen that the tool is able to operate properly and can be useful for the industrial world. (author)
001^ID2500070
008^S36/01/I/M/U
009^M
100^Amalia, Beta
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The effect of sputtering gas composition on surface properties Bi-layer N/WN coating on SS 316L
230^Pengaruh komposisi gas sputtering terhadap sifat permukaan lapisan Bi-layer N/WN pada baja tahan karat SS 316L
300^INIS-ID--0129
403^2023
500^55 p.
600^(IN)
610^33 refs.; 27 figs.; 12 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SPUTTERING; GASES; CHEMICAL COMPOSITION; SURFACE AIR; COATINGS; STAINLESS STEEL-316L; IMPLANTS; RADIATION SOURCE IMPLANTS; BONE TISSUES; SKELETON
009^X/EN
860^The need for the use of orthopaedic implants in bone medicine is increasing. The materials used include SS 316L because the price is relatively cheap compared to other metal implant materials. The weakness of SS 316L is low hardness and not resistant to wear so that it cannot be used for a long period of time. Therefore, it needs treatment to improve its surface quality so that it can increase its hardness and wear resistance. The treatment was carried out with a plasma nitriding process and followed by DC sputtering to form a bi-layer N/WN layer. The plasma nitriding process was carried out at a temperature of 400 #Degree Sign#C, a pressure of 1.6 mbar and a time of 4 hours, while the DC sputtering process varied the composition of the Ar:N_2 gas mixture, namely: 80 %Ar:20 %N_2, 70 %Ar:30 %N_2, and 60 %Ar:40 %N_2. The test results show that the N/WN bi-layer coating can increase the hardness and wear resistance, the highest hardness increase in the ratio of 70 %Ar:30 %N_2 gas mixture composition is 1567.88 VHN from the raw material 223.46 VHN, and the wear rate is 4.3#Multiplication Sign#10"-"6 mm"2/kg from the raw material 28.95 mm"2/kg. The wettability test results obtained a contact angle value of 70.3140 from the raw material 40.740 which means this treatment increases wettability. Based on the XRD test results show that the N/WN bi-layer coating produces a layer of new phases/compounds including W, WN, Fe_2N, Fe_3N, CrN and Cr_2N which can increase the hardness and wear resistance of the SS 316L surface. (author)
001^ID2500071
008^S61/01/I/M/U
009^M
100^Zakiyah, Daffa Azhar
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The effect of filter variations on radiography image quality with the Computed Radiography (CR) method using betatron
230^Pengaruh variasi filter terhadap kualitas citra radiografi dengan metode Computed Radiography (CR) menggunakan betatron
300^INIS-ID--0130
403^2023
500^85 p.
600^(IN)
610^64 refs.; 33 figs.; 18 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^BIOMEDICAL RADIOGRAPHY; INDUSTRIAL RADIOGRAPHY; COMPUTERIZED TOMOGRAPHY; BETATRONS; IMAGES; IMAGE PROCESSING; SCATTERING; RADIATION SCATTERING ANALYSIS; IRRADIATION
009^X/EN
860^Radiographic contrast is one of the factors that affect the quality of radiographic images. Radiographic contrast can continue to decrease, causing radiographic images to be unable to display dark and light areas clearly. Decreased radiographic contrast can be caused by scatter radiation. One of the measures to reduce the potential for scattered radiation is to use filters. The purpose of this study was to determine the effect of the type of filter material, filter thickness, and radiation energy on the quality of radiographic images with the CR irradiation method using Betatron SEA 7. The types of radiographic filter materials are Aluminum (Al), Stainless Steel (SS), and Lead (Pb). ) with a thickness of 3 mm, 6 mm and 9 mm respectively. The irradiation energy is 3 MeV, 4 MeV, 5 MeV, and 6 MeV. The irradiation object material is a steel plate with a thickness of 25 mm. The results showed that the SS filter with a thickness of 3 mm was the most effective filter in producing the highest contrast value, namely 14997 at 3 MeV energy, 17867 at 4 MeV energy, 19461 at 5 MeV energy, and 13581 at 6 MeV energy with a percentage increase in contrast value. respectively - energy of 36.2 %, 65 %, 39.5 %, and 22.2 %. From this research it can be concluded that radiation energy, material type, and filter thickness have an influence on the quality of radiographic images. (author)
001^ID2500072
008^S37/01/I/M/U
009^M
100^Mukti, Danu Anggara
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The effect of N/TiN Bi-layer coating gas composition on corrosion properties and bacterial growth of stainless steel 316L
230^Pengaruh komposisi gas pembentuk lapisan Bi-layer N/TiN pada stainless steel 316L terhadap sifat korosi dan pertumbuhan bakteri
300^INIS-ID--0131
403^2023
500^54 p.
600^(IN)
610^15 refs.; 34 figs.; 5 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^LAYERS; COATINGS; GASES; CORROSION; STAINLESS STEEL-316L; BONE FRACTURES; OSTEOPOROSIS; CORROSION RESISTANCE; THIN-LAYER CHROMATOGRAPHY; THIN FILMS
009^X/EN
860^Cases of bone fractures are common in Indonesia due to various reasons such as osteoporosis and high levels of accidents. Bone healing can be achieved through bone implantation, with Stainless Steel 316L being a commonly used metal due to its corrosion resistance, physical properties, mechanical properties, and easy-to-clean surface. However, improvements are necessary to enhance its qualities, including corrosion resistance and bacterial growth suppression. One effective method for improving corrosion resistance and suppressing bacterial growth on stainless steel 316L is the growth of thin layers through surface treatment. This can be achieved using methods such as plasma nitriding and plasma sputtering. Plasma nitriding process forms nitride layers of metals (FeN and CrN), while plasma sputtering process forms TiN layers, resulting in the formation of N/TiN bi-layer coating on the surface of SS 316L samples. The samples in this study are disc shaped with a thickness of 5 mm and a diameter of 14 mm. Plasma nitriding is conducted at a temperature of 400 #Degree Sign#C, gas pressure of 1.6 mbar, and a duration of 4 hours. Sputtering process is performed using Ti target and sputter gas mixture of Ar and N_2 with compositions of 100 %Ar, 80 %Ar : 20 %N_2, 70 %Ar : 30 %N_2, and 60 %Ar : 40 %N_2. Specifically, for samples sputtered with 70 %Ar : 30 %N_2, additional sputtering with 100 %Ar using AgCu target is applied. Test results indicate that the highest corrosion resistance (lowest corrosion rate) is achieved through the nitriding and sputtering process with 60 %Ar : 40%N_2 gas composition, resulting in 0.00074402 mm/a compared to the raw material's 0.08675 mm/a. The optimal condition for bacterial growth suppression is achieved through nitriding and sputtering processes with 60 %Ar : 40%N_2 and 70 %Ar : 30 %N_2 gas compositions, along with the addition of 100 %Ar sputtering using AgCu target. This condition yields 1 colony compared to the raw material's 72 colonies. XRD test results of the N/TiN bi-layer coating resulting from the nitriding and sputtering process reveal new phases including Ti, TiN, CrN, Cr_2N, Fe_2N, Fe_3N, and Fe_4N, which enhance corrosion resistance and suppress bacterial growth. (author)
001^ID2500073
008^S46/01/I/M/U
009^M
100^Grahita, Defriska Naura Ayu
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of the automated portable gamma scan tomography tool for scaling inspection in geothermal pipes
230^Rancang bangun otomatisasi pada alat tomografi gama scan portable untuk pemeriksaan scaling pada pipa panas bumi
300^INIS-ID--0132
403^2023
500^204 p.
600^(IN)
610^31 refs.; 106 figs.; 6 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; PORTABLE EQUIPMENT; GAMMA RADIOGRAPHY; GAMMA RADIATION; CAT SCANNING; COMPUTERIZED TOMOGRAPHY; INSPECTION; GEOTHERMAL SYSTEMS; PIPES; GEOTHERMAL INDUSTRY
009^X/EN
860^According to the Ministry of Energy and Mineral Resources, Indonesia is one of the countries which possessed the largest geothermal resources in the world, with estimated #+-# 28.5 GWe in 2018, which is widely utilized by the geothermal industry. One of the crucial problems that geothermal industries encounter is the formation of scaling in the pipes. This has resulted delays in the geothermal production process, creating material losses for the company and uneven distribution of electricity in Indonesia. This research aims to produce a prototype for automation system of a portable gamma scan tomography tool to carry out scaling inspection in geothermal pipes, so that potential scaling problems can be found earlier and workers do not need to be exposed to radiation when taking tomography datas. The automation system is designed using Arduino Mega 2560 as the microcontroller and radiation counter, stepper motors as the actuator, NaI(Tl) detector for radiation detection, limit switch as a trigger for setting up tool to the zero point position, HMI as the interface, and a microSD card as the tool to store radiation count datas. The automation system will drive NaI(Tl) detector and source collimator to scan the radiation along the pipe diameter in maximum 32 projections. Examination on the accuration and precision of the system actuator will be done by executing translational and rotational movements for 5 times in 32 projections, meanwhile the radiation-counting test is carried out by detecting radiation at 5 random points to test the stability of the radiation-counting system. The result of the examination is analyzed using quantitative statistical methods which is RMSE and Standard Deviation for accuration and precision value of the actuator, also Chi Square for the stability of radiation-counting system. This research has managed to build automation for a portable gamma scan tomography tool with an accuracy value of 95,12 %, a precision value of 93,58 %, and the stability of the radiation-counting system is in the acceptability range of 3,325 #approx# 16,919 with confidence level of 95 %. (author)
001^ID2500074
008^S42/01/I/M/U
009^M
100^Ardhika, Dimas Rizky
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Comparative analysis of concrete viability using ultrasonic pulse velocity and X-rays
230^Analisis perbandingan kelayakan beton menggunakan ultrasonic pulse velocity dan sinar-X
300^INIS-ID--0133
403^2023
500^60 p.
600^(IN)
610^34 refs.; 11 figs.; 13 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^COMPARATIVE EVALUATIONS; CONCRETES; VIABILITY; ULTRASONIC WAVES; PULSES; VELOCITY; GAMMA RADIATION; ULTRASONIC TESTING; IRRADIATION; IMAGES
009^X/EN
860^The quality of concrete is greatly influenced by the constituent materials and their ratio, so it must be tested to check the quality of concrete to be used. Damage testing with ultrasonic pulse velocity is one of the methods to test the quality of concrete. Ultrasonic pulse velocity testing only displays the signal from the device and it is not known how the image of the concrete conditions in the building, the need for comparison between UPV and X-rays is where it can display fast propagation data and image results on each specimen because checking concrete is only seen by the value of ultrasonic waves not yet on the visual image of the concrete. In this study, ultrasonic pulse velocity is used to determine the feasibility of concrete, and the next method is to irradiate concrete using X-rays in order to determine the results of radiographic images on concrete specimens K250 and K725. Concrete specimens type K250 and K725 from the ultrasonic pulse velocity test results are then compared with the results of radiographic images using X-rays in order to obtain data on the feasibility of certified concrete specimens tested using ultrasonic pulse velocity with variable comparisons using X-ray aircraft. Referring to the irradiation with exposure experiment using step wedge concrete for firing parameters on full cube concrete and obtained gray value and signal to noise ratio values used as a reference for the suitability of concrete and ultrasonic pulse velocity results obtained fast propagation. By using the step wedge calculation, the gray value vulnerability value is taken as 55,000 to 60,000 and the signal to noise ratio value is above 70 with the calculation of 90kV, 6mA, 600mm SFD ready to be applied to full concrete cubes. (author)
001^ID2500075
008^S46/01/I/M/U
009^M
100^Adhiwangsa, Farid Zaki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Programming for exposure chart modelling in conventional X-ray radiography
230^Pemrograman untuk pemodelan kurva penyinaran pada radiografi sinar-X konvensional
300^INIS-ID--0134
403^2023
500^97 p.
600^(IN)
610^40 refs.; 22 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^PROGRAMMING; SIMULATION; DIAGRAMS; X-RAY RADIOGRAPHY; FILMS; TUBES; GEOMETRY; IMAGES; STEELS; ALUMINIUM
009^X/EN
860^In radiography, an exposure chart is needed to determine the correct exposure. The creation of exposure chart so far requires a lot of film. To reduce the use of film, a program was created that utilizes the principles of radiographic exposure in the form of the relationship between tube current, tube voltage, exposure time, film characteristics curve, and geometry principles. The program was validated through curve fitting and Mean Absolute Percentage Error (MAPE) by comparing the density of the specimen radiograph image with the exposure chart generated by the program. The generated exposure chart are the exposure chart for steel with voltages of 120 kV, 130 kV, 140 kV, 150 kV, and 160 kV and exposure chart for aluminum material with voltages of 110 kV, 120 kV, 130 kV, 140 kV, and 150 kV for Rigaku 250 EGS-3 X-ray machine. The program has successfully generated the exposure chart with the highest error value of 6.46 % for steel material and 40.03 % for aluminum material and a coefficient of determination of 0.97 for steel and 0.95 for aluminum. (author)
001^ID2500076
008^S36/01/I/M/U
009^M
100^Dafanabawi, Firdaus
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^The effect of cooling media on the corrosion rate of low carbon steel welding
230^Pengaruh media pendingin terhadap laju korosi hasil las-lasan baja karbon rendah
300^INIS-ID--0135
403^2023
500^59 p.
600^(IN)
610^23 refs.; 21 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^COOLING; CORROSION; LOW CARBON-HIGH ALLOY STEELS; STEELS; WELDING; CARBON STEELS; GRAIN SIZE; VICKERS HARDNESS; MICROHARDNESS; COOLING SYSTEMS
009^X/EN
860^Carbon steel is widely used for industrial purposes because it has strong, hard and brittle properties. One of the application processes that is often carried out on steel is welding, but the quality of the welds is greatly influenced by the cooling speed. So this research was conducted to explain the relationship between the post-welding cooling process and the grain size and corrosion rate to improve previous studies that focused more on the level of macro hardness as measured using a vicekrs hardness tester. In previous studies it was proven that the higher the heat input and the faster the process, the material tends to have a high hardness value. So that in this study carried out variations of cooling media using air media, ice water media, oil media, and salt water media. From the results of the study it was found that the best (lowest) corrosion rate was obtained with the material that was given a preheating treatment then cooled using air with a corrosion rate value of 0.3296 mm/a. For the hardness profile, cooling using salt has the highest hardness value of 251.20 VHN with an increase of 28.78 % from the initial material, this is also evidenced by the size of the microhardness which can be known from the grain size, where the salt cooling media has the smallest grain size with a size of 16 #Greek Small Letter Mu#m. (author)
001^ID2500077
008^S42/01/I/M/U
009^M
100^Saputra, Gabreal
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Characterization of pipe scale material density by gamma parallel beam tomography method
230^Karakterisasi densitas material kerak pipa dengan metode tomografi gamma paralel beam
300^INIS-ID--0136
403^2023
500^43 p.
600^(IN)
610^20 refs.; 18 figs.; 1 tab.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^PIPELINES; PIPES; BEAMS; GAMMA RADIATION; TOMOGRAPHY; IMAGES; SCALING; GEOTHERMAL INDUSTRY; SILICA; CALCITE
009^X/EN
860^Tomography is a cross-sectional imaging of an object from transmission and reflection data obtained by measuring the object from many different directions. Tomography is an effective method to investigate pipe scaling in the geothermal industry. The most common scaling in geothermal pipes in silica (SiO_2_) and calcite (CaCO_3_). The disruption of fluid flow due to scale in the pipe can cause an increase in pressure and temperature that allows the pipe to burst. Image reconstruction from previous research using the Filtered Back Projection (FBP) method can be used as starting data. Image reconstruction uses filter variations and interpolation variations to produce image recommendation results for the benefit of industry and further research. The image recommendation results show that the hann filter is recommended for optimizing image results with a standard deviation value of 7.382 for pipe wall data and 4.467 for pipe crust data. Meanwhile, the use of deviation using overall data and sample data. Dor overall data, it is recommended to use linear interpolation with a standard deviation of 4.212 on the pipe wall and 13.255 on the pipe crust. Meanwhile, for sample data, it is recommended to use pchip interpolation with a value of 48.201. (author)
001^ID2500078
008^S42/01/I/M/U
009^M
100^Haryadhany, Gema
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design mechanical system of ultrasonic testing scanner for pipe
230^Rancang bangun sistem mekanik ultrasonic testing scanner untuk pipa
300^INIS-ID--0137
403^2023
500^68 p.
600^(IN)
610^18 refs.; 58 figs.; 16 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; MECHANICAL FILTERS; MECHANICAL ENGINEERING; ULTRASONIC TESTING; IMAGE SCANNERS; RADIOISOTOPE SCANNERS; PIPES; NONDESTRUCTIVE TESTING; INSPECTION; CARBON STEELS
009^X/EN
860^Along with the development of technology that has changed to machine technology has an influence on the industrial world. The industrial world is now familiar with automation technology that uses machines to replace human labor. In the world of Non-Destructive Test (NDT) automation technology is also needed so that operators can perform inspections more safely and efficiently. The purpose of this research is to optimize the design of an orbital drive system for inspection of welds on Carbon Steel pipes in its work area. This research is carried out from calculating torque, calculating friction force, determining the mechanical system, designing tools using Autodesk Inventor. Then perform the manufacturing process, namely: material cutting, shaft making, assembly, programming. The tool was tested on the surface of a pipe with a diameter of 15 In. Testing is done by giving commands to the tool so that it moves around the pipe surface clockwise. data collection. The tool that has been made has dimensions of 213 mm long, 392 mm wide, and 70 mm high with a weight of 3.5 kg. The designed tool can scan as far as 650 mm (195.5#Degree Sign#) on a pipe with a size of 15 inches. In Index Direction testing using a normal probe, the signal that appears at the initial position is always higher than the probe that is in the final position. In Index Direction testing using a 70#Degree Sign# angle probe, the results obtained are more stable even though there are many noise signals whose height almost matches the discontinuity signal. (author)
001^ID2500079
008^S36/01/I/M/U
009^M
100^Rahmansyah, Harizt
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and development of an automated GTAW welding system based on PLC for irradiation capsule
230^Rancang bangun sistem otomatisasi pengelasan GTAW berbasis PLC untuk kapsul iradiasi
300^INIS-ID--0138
403^2023
500^112 p.
600^(IN)
610^29 refs.; 30 figs.; 16 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; WELDING; IRRADIATION; CAPSULES; IRRADIATION CAPSULES; MACHINERY; INTERFACES; AUTOMATION; RADIOISOTOPES; ELECTRIC MOTORS
009^X/EN
860^The radioisotope production process using the irradiation method requires a container called irradiation capsules. The manufacturing process of irradiation capsules at PRTRRB-BRIN is still doing manually, which makes it dependent on certified welders. The limitation of certified welding experts causes a decreasing level of productivity and quality of irradiation capsules produced. This research aims to design an automation of GTAW welding system based on PLC for irradiation capsules so to reduce dependence on certified welding experts. The automation system is equipped with human machine interface (HMI) software to facilitate communication between the operator and the GTAW welding machine automation system. Three NEMA 23 stepper motors are used as actuators of the GTAW welding machine mechanical system. The GTAW welding machine automation system for welding irradiated capsules implements a manual welding method, which begins with the initial melting process of the base material followed by a straight welding process until the welding cycle has been reached. Accuracy and precision values are more than 90 % for axis testing of GTAW welding machine. While in the simulation of irradiation capsule welding, the PLC ladder program is able to operate the mechanical system of the GTAW welding machine in accordance with the designated work steps. Based on these tests, it can be concluded that the designed GTAW welding machine automation system is capable of carrying out the welding process of irradiated capsules. (author)
001^ID2500080
008^S22/01/I/M/U
009^M
100^Shindanu, I Gusti Ngurah Putu Arya
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of the implementation of risk based inspection on heat exchanger EA-8701 C type B based on management management variations in petrochemical companies
230^Analisis penerapan risk based inspection pada bagian shell heat exchanger EA-8701 C type B berdasarkan variasi pengelolaan managemen di perusahaan petrochemical
300^INIS-ID--0139
403^2023
500^111 p.
600^(IN)
610^10 refs.; 17 figs.; 44 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^HAZARDS; IMPLEMENTATION; INSPECTION; HEAT EXCHANGERS; PETROCHEMICALS; POLYMERS; COOLING SYSTEMS; CALCULATION METHODS; SAFETY; SECURITY
009^X/EN
860^The petrochemical industry is an industry that produces products from the organic chemical industry which are raw materials for the polymer industry, with basic raw materials sourced from the processing of oil and natural gas (natural gas). In the installation of a petrochemical industry there is a heat exchanger, which has a large enough temperature and pressure. Because it has a large enough temperature and pressure, an analysis of the application of Risk-Based Inspection is needed to reduce the risk level of the cooling equipment system so as to ensure the safety and security of using the heat exchanger. Therefore, a research was made. ANALYSIS OF THE APPLICATION OF RISK BASED INSPECTION ON HEAT EXCHANGER EA-8701 C TYPE B BASED ON MANAGEMENT MANAGEMENT VARIATIONS IN PETROCHEMICAL COMPANIES with the aim of obtaining risk values and the influence of management factor values on risk levels. This research method uses a quantitative calculation method, where the calculations obtain the Probability of Failure (POF) and Consequence of Failure (COF) values which are translated into a risk matrix with medium risk level results for small factor management values, medium risk level for factor management values, medium, the risk level is medium for the management factor value is high, this shows no change to the risk level matrix but there is a change to the risk value. (author)
001^ID2500081
008^S43/01/I/M/U
009^M
100^Vito, Juan
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and manufacturing of prototype control and mechanical system of fruit irradiation facility on low energy electron beam machine
230^Rancang bangun purwarupa sistem kendali dan mekanik fasilitas iradiasi buah pada mesin berkas elektron energi rendah
300^INIS-ID--0140
403^2023
500^68 p.
600^(IN)
610^32 refs.; 27 figs.; 10 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; MANUFACTURING; RADIATION MONITORING; MECHANICAL ENGINEERING; FRUITS; IRRADIATION; ELECTRON DIFFRACTION; ELECTRON BEAMS; IRRADIATION PROCEDURES; RADIATION DOSES
009^X/EN
860^The irradiation process requires irradiation facilities that can irradiate evenly. In PRTA-BRIN the irradiation process using a low energy electron beam machine can only be performed for sheet samples, and cannot irradiate three-dimensional samples. Research design prototype control system and mechanical irradiation of fruit facilities on low energy electron beam machine is done to irradiate the fruit automatically, accurately, and precisely according to the needs of radiation dose. In this study the mechanical system of fruit irradiation facility consists of two conveyors and a pair of rollers using a PLC-based control system equipped with human machine interface (HMI) software that serves to facilitate the irradiation process. Irradiation facility begins with parameter setting and control execution according to input parameters. The results of the function test using fruit with a diameter of 8 cm showed the conveyor is functioning properly and the roller and UV lamp work in accordance with the input parameters but the stepper motor actuator linear actuator has not worked in accordance with the program so that the program can not repeat the cycle. (author)
001^ID2500082
008^S42/01/I/M/U
009^M
100^Rahman, Marwan Shafiyyur
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Development of an inverse kinematic algorithm for SCARA robot arm movement in the process of moving the radiation shield on the INIL
230^Pengembangan algoritma pergerakan lengan robot SCARA berbasis inverse kinematic untuk proses pemindahan penahan radiasi pada INIL
300^INIS-ID--0141
403^2023
500^64 p.
600^(IN)
610^16 refs.; 48 figs.; 9 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^COMPUTERIZED SIMULATION; PARTICLE KINEMATICS; REMOTE HANDLING; ROBOTS; CONTROL SYSTEMS; SIMULATION; ALGORITHMS; CALCULATION METHODS; LEARNING
009^X/EN
860^Internet Nuclear Instrumentation Laboratory INIL) is a remote laboratory developed to support the learning process of nuclear instrumentation without having to come to the laboratory. SCARA robot arm which is one of the components of INIL is still not functioning optimally so a better control system is needed. It is necessary to develop an inverse kinematic-based robot arm movement system that has more than 90 % accuracy and precision. This research will include the stages of designing inverse kinematic algorithms, serial communication between Python and Arduino and testing the accuracy and precision of robot movements using statistical analysis. This research is able to produce a SCARA robot arm system that can be moved using the inverse kinematic method calculated using python and then sanded via serial communication with 92,45 % accuracy and 98,46 % precision. (author)
001^ID2500083
008^S42/01/I/M/U
009^M
100^Akbar, Mohammad Hafidz
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design mechanical system robotic Arm of pH control for radiopharmaceutical "1"5"3Sm-EDTMP preparation
230^Rancang bangun sistem mekanik lengan robot pengatur pH untuk preparasi radiofarmaka "1"5"3sm-EDTMP
300^INIS-ID--0142
403^2023
500^172 p.
600^(IN)
610^33 refs.; 97 figs.; 26 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; MECHANICAL ENGINEERING; ROBOTS; ARMS; RADIOPHARMACEUTICALS; SAMARIUM 153; SKELETON; NEOPLASMS; SAFETY; PERSONNEL
009^X/EN
860^Samarium-153-EDTMP ("1"5"3Sm-EDTMP) is a radiopharmaceutical utilized in the treatment of bone metastasis cancer. The only institution that produces "1"5"3Sm-EDTMP radiopharmaceutical in Indonesia is the Center for Research on Radioisotope Technology, Radiopharmaceuticals, and Biodosimetry (PRTRRB). The high incidence of bone metastasis cancer patients in Indonesia does not match the level of production of "1"5"3Sm-EDTMP radiopharmaceuticals. Additionally, the production process of "1"5"3Sm-EDTMP radiopharmaceuticals is restricted due to safety concerns for radiation workers regarding radiation exposure during the preparation of "1"5"3Sm-EDTMP radiopharmaceuticals. Therefore, this research aims to increase the production of "1"5"3Sm-EDTMP radiopharmaceuticals by designing a robotic arm system to control pH. The study involves 3D design, fabrication, structural analysis, as well as accuracy and precision testing. The result of this research is a mechanical robotic arm system design, consisting of a cylindrical robotic arm equipped with stepper motor actuators and servo motors. The system is controlled using an Arduino-based control system, achieving accuracy and precision levels of 96.21 % and 98.03 % respectively. (author)
001^ID2500084
008^S46/01/I/M/U
009^M
100^Bukhori, Muhammad Almas
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of automatic dispensing of Iodium-131 oral radiopharmaceuticals
230^Rancang bangun otomatisasi dispensing Iodium-131 sediaan oral
300^INIS-ID--0143
403^2023
500^120 p.
600^(IN)
610^55 refs.; 35 figs.; 4 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; AUTOMATION; ODORANT DISPENSERS; ORAL ADMINISTRATION; ORAL CAVITY; RADIOPHARMACEUTICALS; IODINE 131; THERMIONIC EMITTERS; RADIOISOTOPES; CONTAMINATION; RADIATION DOSES
009^X/EN
860^One of the radioisotopes utilized for radiopharmaceutical purposes in Indonesia is the compound labelled as Iodine-131 or I"1"3"1, which functions as both a gamma emitter and a beta emitter. The production of I"1"3"1 radioisotope radiopharmaceuticals involves various processes, among which the dispensing process is employed. Currently, the fabrication of radioisotope radiopharmaceuticals is executed manually by human operators directly. The manual approach can engender an escalation in the potential for product contamination, continuous radiation exposure, and dispensing errors. A prospective resolution to these issues involves the development of an automated Iodine-131 dispensing system, thereby yielding a vial bottling process with a precision and accuracy exceeding 90 %, while simultaneously circumventing dispensing errors. In this context, DC motors and stepper motors are incorporated within the automated dispensing system, with each component serving a distinct function within the respective mechanical module. Sensors are deployed to attain the desired levels of precision and accuracy. The dispensing program is formulated with adaptable filling variables aimed at obtaining empirical data regarding the precision and accuracy of the dispensing process. Empirical data pertaining to dispensed volume is subjected to accuracy and precision evaluations within the vial tubes. Through evaluations involving transfer volumes of 1 ml, 2 ml, and 3 ml, the obtained outcomes reflect commendable accuracy and precision levels. The outcome of these device evaluations has yielded an average accuracy value of 80.19 % and an average precision value of 99.78 %. (author)
001^ID2500085
008^S36/01/I/M/U
009^M
100^Iqbalsyah, Muhammad
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Simulation of nitrogen ion implantation in Ti-6Al-4V material with SRIM software for orthopedic implant application
230^Simulasi implantasi ion nitrogen pada material Ti-6Al-4V dengan perangkat lunak SRIM untuk aplikasi implan ortopedi
300^INIS-ID--0144
403^2023
500^71 p.
600^(IN)
610^50 refs.; 22 figs.; 11 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^SIMULATION; IMPLANTS; NITROGEN IONS; TITANIUM; ALUMINIUM; BIOLOGICAL MATERIALS; TITANIUM ALLOYS; WEAR RESISTANCE; IMPURITIES; ION IMPLANTATION
009^X/EN
860^Chemical stability, mechanical properties, and biocompatibility of a material determine the success of biomaterials for orthopedic implants. Titanium alloys are widely used as orthopedic implants but have a low level of wear resistance. One of the material surface improvement techniques is ion implantation technique. Ion implantation technique has the advantage of being a fast process, can be done at room temperature, and provides ease of controlling impurities in the target material. In this study, nitrogen ion implantation was simulated through Stopping and Range of Ions in Matter (SRIM) software using energies of 60 keV, 50 keV, 40 keV, 30 keV, 30 keV, and 10 keV on Ti-6Al-4V material to determine the relationship between energy and range and obtain maximum ion implantation parameters. Simulation results show that the relationship between ion implantation energy and penetration distance is linear. Ion implantation parameters using a composition of 45 % nitrogen ions and 55 % titanium atoms by the multi-energy method more effectively improved the surface properties of Ti-6Al-4V for orthopedic implant applications than the mono-energy method. (author)
001^ID2500086
008^S61/01/I/M/U
009^M
100^Syafrizal, Muhammad Rifki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Image quality analysis of Agfa D7 and Fuji XD100 radiographic films irradiated with X-rays
230^Analisis kualitas citra film radiografi Agfa D7 dan Fuji XD100 hasil penyinaran dengan sinar-X
300^INIS-ID--0145
403^2023
500^89 p.
600^(IN)
610^28 refs.; 54 figs.; 12 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^IMAGES; RADIATION DOSES; RADIOTHERAPY; XEROGRAPHY; X-RAY DETECTION; X-RAY RADIOGRAPHY; FILM DOSIMETRY; MEASURING METHODS; DOSIMETRY; OPTIMIZATION; PHOTON BEAMS
009^X/EN
860^The selection of film brands in radiographic tests is currently still based on contractual agreements between clients and radiographic test service providers, and there is no adequate information regarding the quality of images produced by film brands available on the market. This study aims to determine the quality of radiographic images on films that are often used in radiographic tests in the industry, namely Agfa D7 and Fuji XD100 films that have been irradiated by X-rays. The parameters tested in this study are density, contrast, latitude, and sensitivity. This research uses SWSV (single wall single viewing), DWSV (double wall single viewing) and DWDV ellipse (double wall double viewing) irradiation techniques using plate, pipe, and step wedge materials. This test was conducted with the same current, voltage, irradiation time, and environmental conditions for both brands of film on each material. The irradiation voltage (kV) used was in the range of 100-160 kV with the time adjusted to the thickness of the material being tested. Processing of the irradiated film was carried out using a washing chart according to the film brand with the temperature used at 68 #Degree Sign#F. The test results for the step wedge obtained the average deviation of density in Agfa D7 film by 3.3 % and Fuji XD100 film by 2.9 %, the average contrast value of Agfa D7 film by 0.52 and Fuji XD100 film by 0.54, as well as better latitude in Fuji XD100 film characterized by more latitude produced on the step wedge for greater thickness. While the Agfa D7 film has an advantage in the average value of sensitivity produced using the test material which is 1.22 % smaller than the Fuji XD100 film which is 1.36 %. (author)
001^ID2500087
008^S42/01/I/M/U
009^M
100^Abduh, Muhammad Widyasworo Wahab
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design pipe support on system MIG welding automation
230^Rancang bangun dudukan pipa pada alat orbital MIG welding otomation
300^INIS-ID--0146
403^2023
500^63 p.
600^(IN)
610^24 refs.; 27 figs.; 7 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; PIPES; AUTOMATION; GAS METAL-ARC WELDING; GASES; PHOTOGRAPHY; STAINLESS STEELS; WELDED JOINTS; CALCULATION METHODS; MECHANICAL ENGINEERING
009^X/EN
860^Automatic drive systems on orbital welding for pipes, requires a pipe holder so that the pipe position can be horizontal and linear for welding to work properly. Development from previous research where the pipe holder system in the form of a jack is less strong, and there is no pipe clamp, therefore in this study aims to design a pipe holder for orbital motion MIG welding automation. This research was conducted from calculating and determining the mechanical system, tool design using solid work, Manufacturing process, machining and assembly. This research successfully made a pipe holder on the MIG Welding automation orbital tool with aluminum material with pipe specifications with dimensions of 114 mm outer diameter and 4 mm thick, which have been determined in the previous final project, with the pipe chuck connection method using bolts and nuts. (author)
001^ID2500088
008^S42/01/I/M/U
009^M
100^Pradana, Rendra Agung
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design of eddy current bobbin probe with various coil configurations to detect discontinuities in pipes
230^Rancang bangun bobbin probe eddy current dengan variasi konfigurasi kumparan untuk mendeteksi diskontinuitas pada pipa
300^INIS-ID--0147
403^2023
500^78 p.
600^(IN)
610^20 refs.; 46 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; PROBES; ELECTRIC COILS; CONFIGURATION; PIPES; MAGNETIC FIELDS; SAMPLE HOLDERS; CATALYTIC CRACKING; PERSONNEL; MAGNET COILS
009^X/EN
860^The principle of eddy current engineering is based on the interaction between the magnetic field source and the test material. This interaction induces an eddy current in the test specimen. Researchers intend to make a special bobbin probe type probe to detect discontinuities in pipes with an inner diameter of 1 inch to detect circumferential crack and volumetric defects so as to make it easier for industrial workers to inspect pipes with a diameter of 1 inch. Using variations of coil arrangement 1 parallel 6 series and 1 parallel 2 series with copper wire diameter 0.20 mm and a total of 12 coils, this variation was carried out with the aim of determining the effect of coil arrangement on the ability to detect discontinuities in pipes. The probe body is made of acrylic, while the probe casing is made of nylon. Using a test specimen of 304 stainless steel pipe with a thickness of 2.1 mm and carbon steel pipe with a thickness of 4 mm. This research has succeeded in designing two eddy current bobbin probes with specifications; absolute probe bobbin type, probe diameter 1 inch, probe length 110 mm, frequency 22 kHz - 55 kHz, gain 45 dB. This probe is able to detect circumferential cracks and volumetric defects on 304 stainless steel tubes with a diameter of 31.7 mm with defect depths of 10 %, 20 %, 40 %, and 60 % for circumferential cracks while for volumetric defects of 100 %, 80 %, 60 %, and 40 %. (author)
001^ID2500089
008^S42/01/I/M/U
009^M
100^Zakaria, Rico Zaky
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Comparative analysis of Rigaku and Eresco X-ray machines radiation exposure rates in enclosed facilities with Monte Carlo simulation
230^Analisis komparasi laju paparan radiasi pesawat sinar-X Rigaku dan Eresco pada fasilitas tertutup dengan simulasi Monte Carlo
300^INIS-ID--0148
403^2023
500^137 p.
600^(IN)
610^50 refs.; 53 figs.; 17 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^COMPARATIVE EVALUATIONS; X-RAY EQUIPMENT; X-RAY RADIOGRAPHY; RADIATION DOSES; MONTE CARLO METHOD; SIMULATION; SHIELDING; SHIELDING MATERIALS; EXPOSURE RATEMETERS
009^X/EN
860^In closed facilities where X-ray machine operate, space geometry and radiation shielding are required according to standards for the control of occupational safety and health by taking into account radiation exposure. Exposure rate calculations can be performed using deterministic (direct exposure rate measurements) and stochastic (Monte Carlo simulation) methods. This study aims to validate X-ray modeling from Monte Carlo simulations using radiation exposure rate data from the Rigaku and Eresco X-Ray Machines. Monte Carlo simulation using the MCNPX nuclear computing software. Meanwhile, the experiment used the Rigaku 250EGS3 and Eresco 65 MF4 X-Rays which were placed in a closed facility by positioning the anode of the X-Rays in the middle of the room. Experimental tests and simulations were carried out at a voltage of 140, 150 and 160 kV with a current of 5 mA. Comparison of the simulation with the experiment based on the division of wall locations, namely walls A, B, C, and D. The results of the comparison using the Mean Absolute Percentage Error (MAPE) method show that 2 of the 8 walls are in the very accurate category, with a percentage of 10 % each, namely on walls A and D in the comparison of the MCNPX simulation with the Rigaku X-Ray Machine experiment. The MCNPX simulation can be used to determine the rate of radiation exposure, but it is necessary to consider the factors causing the high error in this study. (author)
001^ID2500090
008^S61/01/I/M/U
009^M
100^Mubarok, Rizki
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Analysis of Betatron SEA 7 radiography image results based on radiography angle on reinforced concrete
230^Analisis hasil citra radiografi Betatron SEA 7 berdasarkan sudut penyinaran pada beton bertulang
300^INIS-ID--0149
403^2023
500^124 p.
600^(IN)
610^15 refs.; 45 figs.; 20 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^BETATRONS; BIOMEDICAL RADIOGRAPHY; INDUSTRIAL RADIOGRAPHY; COMPUTERIZED TOMOGRAPHY; IMAGES; IMAGE PROCESSING; SCATTERING; RADIATION SCATTERING ANALYSIS; IRRADIATION
009^X/EN
860^In the field of construction and building safety must be prioritised. Therefore, the strength of concrete reinforcement in building pillars must be considered. Standard concrete quality testing is carried out by Non Destructive Test method because this method cannot damage the building structure. One of the Non Destructive Test technologies that can be used is Betatron SEA 7 with Computed Radiography equipment in the form of CRx vision, Rhytm RT and Rythtem Review. Betatron SEA 7 is an aircraft that produces high-energy electron beams or X-rays for non-destructive test activities in closed and open facilities. This study tested 5 concrete samples with 4, 6 and 9 reinforcement variations, and thicknesses of 18.6 cm to 28.6 cm. The irradiation was carried out with an energy of 6.5 MeV and for reinforcement 4 the time used was 360 to 390 seconds, for reinforcement 6 and 9 the time used was 570 to 590 seconds. Angle determination was carried out with angle variations of 10 to 30 degrees. The results of the irradiation were measured on each reinforcement and the measurement of grey value in concrete. From these results, a good grey value is obtained, namely 22984 to 32,768 with an angle of 20#Degree Sign# and the average data of the magnification value that occurs in each reinforcement with a deviation value of less than 10 %, except for reinforcement 9, the deviation value is obtained at 17 %. (author)
001^ID2500091
008^S46/01/I/M/U
009^M
100^Al Farisy, Syahda Khalif
110^Politeknik Teknologi Nuklir Indonesia - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Kec. Depok, Kab. Sleman, Daerah Istimewa Yogyakarta 55281 (ID)
111^Thesis (S.Tr.T.)
200^Design and manufacture of dispensing and distribution Iodine-131 mechanical system with motor drive
230^Rancang bangun sistem mekanik dispensing dan pendistribusian Iodium-131 dengan penggerak motor
300^INIS-ID--0150
403^2023
500^115 p.
600^(IN)
610^34 refs.; 51 figs.; 14 tabs.
611^Available from the Library of the Indonesian Nuclear Technology Polytechnic - BRIN, Jl. Babarsari, Ngentak, Caturtunggal, Depok District, Sleman Regency, Daerah Istimewa Yogyakarta 55281 (ID)
009^9
800^DESIGN; AUTOMATION; ODORANT DISPENSERS; ORAL ADMINISTRATION; ORAL CAVITY; RADIOPHARMACEUTICALS; IODINE 131; THERMIONIC EMITTERS; RADIOISOTOPES; CONTAMINATION; RADIATION DOSES
009^X/EN
860^Iodine-131 is one of the radioactive iodine that is utilized in nuclear medicine. At the Research Center for Radioisotope Technology, Radiopharmaceuticals, and Biodosimetry (PRTRRB), the processing of Iodine-131 is still done manually. This can cause workers to be very at risk of exposure to Iodine-131 radiation. Based on these problems, this research aims to design and manufacture a mechanical system of dispensing and distribution Iodine-131 with a motor drive. This research was conducted with several methods including design, manufacturing process, assembly, and testing of Iodine-131 dispensing and distribution mechanical equipment consisting of conveyors and rotary tables. From the results of the research, a mechanical dispensing system has been made with an average accuracy level of 80.399 %, and an average precision level of 99.524 % for the filling process of 1 ml, 2 ml, 3 ml with the number of motor steps of 500, 1000, and 1500 steps. For the rotary table, the accuracy of bottle position distribution is obtained at 45#Degree Sign#, 90#Degree Sign#, and 180#Degree Sign# rotation with the number of motor steps 45, 90, and 180 steps. And for conveyors can move safely and stably with a motor speed of 45-120 RPM. (author)