超临界水堆典型事故分析

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基金项目:

中核核反应堆热工水力技术重点实验室课题(2013B40)

中核核反应堆系统设计技术重点实验室课题(2014BJ0041)

中央高校基本科研业务专项资金项目(2014BJ0086,2014BJ0087)

Typical Accident Analysis of Supercritical Water-Cooled Reactor

1. North China Electric Power University Nuclear Thermal Safety and Standardization Research Institute, Beijing, 102206, China;
2. Beijing Passive Technology Key Laboratory, Beijing, 102206, China;
3. Science Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 选取中国百万千瓦级超临界水冷堆(CSR1000)为研究对象,以SCAC安全分析程序为基础,编制了SCAC-CSR1000安全分析程序。将计算结果与同堆型计算程序SCTRAN进行对比,验证程序的可靠性;此后进行在能动安全系统控制下的部分失流、汽轮机阀门误关闭、控制棒抽出、冷却剂泵卡轴事故计算。结果表明,CSR1000反应堆在4种瞬态事故下,都能够保证最高包壳温度(MCST)低于1260℃的安全限值;每个事故下第二流程MCST均高于第一流程MCST;汽轮机阀门误关闭事故具有较小的安全边界。
- 中国百万千瓦级超临界水冷堆(CSR1000) /
- 瞬态 /
- 安全 /
- SCAC
Abstract: CSR1000 was selected as the research object. A code named SCAC-CSR1000 has been developed based on the SCAC code. The reliability of the code was verified by comparing the results of SCAC-CSR1000 and SCTRAN. Then the safety analysis was carried out. Five events were selected, that are partial loss of reactor coolant flow, isolation of main steam line, uncontrolled CR withdrawal, reactor coolant pump seizure and loss of feed water heating. By the numerical analysis, it was found that the MCST does not exceed 1260℃, and meets the design safety requirements. The 2nd MCST are higher than the 1st MCST. The isolation of main steam line has the less safety margin.
- China Supercritical-Water-Cooled Reactor 1000（CSR1000） /
- Transient /
- Safety /
- SCAC