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- W3217810478 abstract "• A pre-defueled operation mode after the permanent shutdown was evaluated. • Modeling schemes for MELCOR2.1/SNAP were developed for the pre-defueled operation mode. • The assessment of recirculation line break accident was performed. • The effectiveness of the low pressure core injection system was evaluated. After the operating license of the Nuclear Power Plant (NPP) has expired, a lack of storage capacity of the spent fuel pool (SFP) may occur when the dry storage facilities are not ready. As a result, the fuel of the last cycle will remain in the reactor vessel. When the NPP is under pre-defueled operation mode, it means the vessel head is removed, interconnecting with the upper cavity and SFP via movable gate. Hence, the reactor vessel, upper cavity, and SFP can be treated as an integrated system. This study has developed a MELCOR2.1/SNAP model to analyze the thermal response under the recirculation loop occurring break. There are two decay power conditions in this study: limited condition (7 days after shutdown) and realistic condition (942 days after shutdown). Based on the results of the recirculation line break accident under the limited condition with low-pressure coolant injection (LPCI), the core integrity may be challenged. And the realistic condition is less harsh than the limited condition; the core can be adequately cooled following a loss of coolant at the recirculation line break." @default.
- W3217810478 created "2021-12-06" @default.
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- W3217810478 date "2022-03-01" @default.
- W3217810478 modified "2023-09-23" @default.
- W3217810478 title "The thermal analysis of pre-defueled operation for decommissioning of a BWR4 reactor" @default.
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- W3217810478 doi "https://doi.org/10.1016/j.anucene.2021.108804" @default.
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