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Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

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The main purpose of this study is to investigate reactivity 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 fissile and the associated reactivity effects. The Nuclear Regulatory Commission (NRC) guidance on k-eff being less than 1.0 for spent fuel pools filled with unborated water was the main criterion used in this study. It was found that assemblies with 49.0 GWd/MTU and 5.0 w/o U-235 initial enrichment loaded in Region-II satisfy this criterion. | Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

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Sensitivity studies in spent fuel pool criticality safety analysis for APR-1400 nuclear power plants

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