Neutron transport analysis of C5G7-TD benchmark with PANDAS-MOC

Annals of Nuclear Energy（2022）

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摘要

•A new numerical code, PANDAS-MOC, was developed for the neutron transport analysis.•Steady state and transient analysis were performed using the C5G7-TD benchmark.•Steady state eigenvalue and power distribution were close to the reference results.•Transient reactivity and relative power were well-agreed with the published results.

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关键词

Neutron transport,Transient analysis,PANDAS-MOC,C5G7-TD benchmark

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