3D SN and Monte Carlo calculations of the Utah TRIGA reactor core using PENTRAN and MCNP6

Annals of Nuclear Energy(2021)

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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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