秦山一期核电站小破口冷却剂丧失初因严重事故以及缓解措施的研究

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Study on Severe Accident Progression Induced by SBLOCA and Mitigation Measures for QINSHAN NPP Unit 1

Department of Nuclear Science and System Engineering, School of Mechanics and Power Engineering, Shanghai Jiaotong University, 200030, China

摘要: 采用基于SCDAP/RELAP5的核反应堆严重事故分析平台,分析研究了秦山一期核电站一回路冷段小破口冷却剂流失(SBLOCA)初因导致严重事故进程,并根据美国SAN ONOFRE 核电站的IPE结果以及SURRY的PSA评估结果^[1、2],选择适当的缓解措施,即进行一回路补给水,对该事故做了相应的干预。通过计算分析,对阻止SBLOCA引发的严重事故进程的缓解措施的有效性进行了验证。
- 秦山一期核电站 /
- 小破口冷却剂流失 /
- 严重事故管理 /
- 缓解措施
Abstract: The severe accident, induced by small-break lost-of-coolant accident （SBLOCA） in Qinshan NPP Unit 1, is analyzed by a NPP severe accident simulator developed in this laboratory, based on SCDAP/RELAP5 and PROSYS. By employing the results of USA SAN ONOFRE NPPs IPE and SURRYs PSA, to end the core damage progression and mitigate the consequences of SBLOCA, the primary feed-and-bleed measures for the management of the severe accident induced by SBLOCA is selected, which is verified through the calculation by using the simulator. The results suggest that implementing the feed-and-bleed measures could be available and an effective way to arrest the SBLOCA sequences in Qinshan NPP unit 1.
- Qinshan nuclear power plant unit 1 /
- Small-break lost-of-coolant accident /
- Severe accident management /
- Mitigation measures