Nuclear Safeguards Feasibility Study for a Molten Salt Reactor Using MCNP Modeling and Simulations
Published in Texas A&M University, 2024
Keywords: Nuclear Safeguards, Molten Salt Reactor, Special Nuclear Material, Non-Destructive Assay, MCNP Modeling, Plutonium Quantification, Fission Products, Neutronics
Recommended citation: M. DERMAN, "Nuclear Safeguards Feasibility Study for a Molten Salt Reactor Using MCNP Modeling and Simulations," Master's thesis, Texas A&M University, College Station, TX, USA (2024).
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