Coupled neutronics and thermal-hydraulics simulation of molten salt reactors based on OpenMC/TANSY

Annals of Nuclear Energy(2017)

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摘要
•Two-step scheme for simulation of MSRs based on OpenMC/OpenFOAM.•Accurate geometry modeling capability for both cross sections generation and full-core simulation.•Development of a multi-region and multi-physics code for MSRs based on OpenFOAM.•Calculation and analysis of safety-related parameter βeff and critical fuel concentration.
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关键词
MSRs,Coupled neutronics and thermal-hydraulics analysis,Finite volume method,OpenFOAM,OpenMC
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