RMC - A Monte Carlo Code for Reactor Core Analysis
Annals of Nuclear Energy（2015）
Abstract
•A Monte Carlo reactor analysis code RMC is developed by Tsinghua University.•The criticality benchmark problems have been taken out to test RMC.•Full reactor core benchmarks have been taken out.•A 2-D pin-by-pin full core burnup problem has been taken out.•RMC shows good performances in criticality, burnup and parallel calculations.
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Key words
RMC,Monte Carlo,Reactor analysis,Source convergence,Burnup calculation
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