Study on the Accident of SBO Superimposed by Steam-driven Auxiliary Feedwater Failure Based on RISMC Analysis Method

Wang Zhao; Li Qiongzhe; Guo Jianbing

doi:10.13832/j.jnpe.2023.06.0186

Volume 44 Issue 6

Dec. 2023

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Wang Zhao, Li Qiongzhe, Guo Jianbing. Study on the Accident of SBO Superimposed by Steam-driven Auxiliary Feedwater Failure Based on RISMC Analysis Method[J]. Nuclear Power Engineering, 2023, 44(6): 186-192. doi: 10.13832/j.jnpe.2023.06.0186

Citation:

Wang Zhao, Li Qiongzhe, Guo Jianbing. Study on the Accident of SBO Superimposed by Steam-driven Auxiliary Feedwater Failure Based on RISMC Analysis Method[J]. Nuclear Power Engineering, 2023, 44(6): 186-192. doi: 10.13832/j.jnpe.2023.06.0186

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Study on the Accident of SBO Superimposed by Steam-driven Auxiliary Feedwater Failure Based on RISMC Analysis Method

doi: 10.13832/j.jnpe.2023.06.0186

Nuclear Safety and Operation Technology Center, Suzhou Nuclear Power Research Institute Co., Ltd., Suzhou, Jiangsu, 215000, China

Received Date: 2022-12-23
Rev Recd Date: 2023-07-03
Publish Date: 2023-12-15

Abstract

Abstract

In order to study the safety performance of an in-service CPR1000 nuclear power unit under station blackout (SBO) accident superimposed by steam-driven auxiliary feed water failure, the risk-informed safety margin characterization (RISMC) analysis method is adopted; combining with accident scenario analysis, system reliability analysis, human factor engineering analysis and thermal hydraulic analysis, CARS software coupled with RELAP5 code is used to quantify the safety margin of the unit under accident. The safety performance and safety boundary of the unit under accident scenario is studied. The results show that the RISMC analysis method can effectively analyze the safety characteristics of units, and provide support for the operation and maintenance decision-making of nuclear power plants.
- RISMC,
- Peak clading temperature (PCT),
- SBO,
- Safety analysis

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References(12)

References

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