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| Issue |
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| Vol 50, No 3 (2024): DECEMBER 2024 |
Radiation Dose Calculation Analysis During The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results |
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B. El Azzaoui, O. Kabach, R. Outayad, M. Y. Messous, K. Bergaoui, K. Nbaoui, J. Kadiri, E. Chakir, E. Alibrahmi, A. Kharchaf |
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| Vol 40, No 1 (2014): April 2014 |
Analysis of 99Mo Production Capacity in Uranyl Nitrate Aqueous Homogeneous Reactor using ORIGEN and MCNP |
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A. Isnaeni, M.S. Aljohani, T.G. Aboalfaraj, S.I. Bhuiyan |
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| Vol 51, No 3 (2025): DECEMBER 2025 |
Evaluation of Neutron Flux in Boron Neutron Capture Therapy for a 10-Year-Old Child with Head and Neck Rhabdomyosarcoma Using Monte Carlo Simulation |
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F. M. Salim, E. Hidayanto, W. Setiabudi, F. Arianto |
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| Vol 48, No 2 (2022): August 2022 |
Neutronic Evaluation of Using a Thorium Sulfate Solution in an Aqueous Homogeneous Reactor |
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D. Pérez, D. Milian, L. Hernández, A. Gámez, D. Lorenzo, C. Brayner |
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| VOL 50, NO 1 (2024): APRIL 2024 |
Monte Carlo Methods to Simulate the Propagation of the Created Atomic/ Nuclear Particles from Underground Piezoelectric Rocks through the Fractures Before the Earthquakes |
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A. Bahari, S. Mohammadi, N. S. Shakib, M. R. Benam, Z. Sajjadi |
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| VOL 50, NO 1 (2024): APRIL 2024 |
Neutronic Design Modification of Passive Compact-Molten Salt Reactor |
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R. A. P. Dwijayanto, A. W. Harto |
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| VOL 49, NO 2 (2023): AUGUST 2023 |
Optimizing Neutronic and Photonic Performance in Irradiation Systems of Symmetric TRIGA Cores |
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S. M. Shauddin |
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