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자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제50권 제5호
발행연도
2018.1
수록면
709 - 716 (8page)

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A criticality safety analysis was performed for the APR-1400 spent fuel pool region-II to ensure the safestorage of spent fuel, with credit taken for depletion and in-rack neutron absorbers (Metamic panels). PLUS7 fuel assembly was modeled using TRITON-NEWT of SCALE-6.1. The burnup-dependent crosssectionlibrary was generated under limiting core-operating conditions with 5%-w U-235 initialenrichment. MCNP5 was used to evaluate the neutron multiplication factor in an infinite array of rackcells with the axially nonuniformly burnt PLUS7 assemblies under normal, abnormal, and accidentconditions; including all biases and uncertainties. The main purpose of this study is to investigatereactivity variations due to the critical depletion and reactor operation parameters. The approach, assumptions,and modeling methods were verified by analyzing the contents of the most important fissileand the associated reactivity effects. The Nuclear Regulatory Commission (NRC) guidance on k-eff beingless than 1.0 for spent fuel pools filled with unborated water was the main criterion used in this study. Itwas found that assemblies with 49.0 GWd/MTU and 5.0 w/o U-235 initial enrichment loaded in Region-IIsatisfy this criterion. Moreover, it was found that the end effect resulted in a positive bias, thus ensuringits consideration

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