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Nuclear Safeguards Feasibility Study for a Molten Salt Reactor Using MCNP Modeling and Simulations
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Systematic Uncertainty Quantification Of MCNP Predicted Nuclide Concentrations In Fuel Burnup Simulations
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Feasibility Study of the Conversion of IRT Research Reactor in the Democratic People’s Republic of Korea (DPRK) from Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) Fuel
Citation: D. Lee, "Feasibility Study of the Conversion … [Read more...] about Feasibility Study of the Conversion of IRT Research Reactor in the Democratic People’s Republic of Korea (DPRK) from Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) Fuel
Improvements of Background Neutron Estimation for Mobile Radiological Search Systems by the Exclusion of Fission Events
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