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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 | Abstract
													
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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 | Abstract
													
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				| A. Isnaeni,											M.S. Aljohani,											T.G. Aboalfaraj,											S.I. Bhuiyan | 
			
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								| Vol 48, No 2 (2022): August 2022 | Neutronic Evaluation of Using a Thorium Sulfate Solution in an Aqueous Homogeneous Reactor | Abstract
													
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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 | Abstract
													
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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 | Abstract
													
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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 | Abstract
													
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				| S. M. Shauddin | 
			
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