3D SN and Monte Carlo calculations of the Utah TRIGA reactor core using PENTRAN and MCNP6
Annals of Nuclear Energy(2021)
摘要
•3D SN Method TRIGA Reactor Core Calculation.•Criticality Problem Energy Group Collapsing and Geometry Homogenization.•Computational Verification of TRIGA Core Calculation.•Experimental Validation of 3D SN Method TRIGA Reactor Core Calculation.•High Performance Parallel Computation.
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关键词
UUTR,PENTRAN,MCNP6,3-D Core flux distribution,Criticality,Eigenvalue
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