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RISComparative Study on the Impact of endf/b-vii.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled Accelerator-Driven System Calculation Results Using Monte Carlo Method Codes
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A new design of a small power accelerator-driven system (ADS) using inert matrix fuel—ceramic–ceramic matrix (CERCER) and ceramic-metallic matrix (CERMET) was proposed in our previous work for high transmutation rate, small ...
Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: 200 MWth lead-cooled fast reactor (LOTUS) reactor core is a small modular lead-cooled fast reactor with designed power of 200 MWth under development at Vietnam National University (VNU) University of Science, Hanoi for a ...
Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A small modular lead-cooled fast spectrum core concept called Advanced lead-cooled modular nuclear reactor (ALMANAR) designed to produce 45 MWth power for 22 years operating without refueling was proposed in a previous ...