摘要
通过引进及自行研制,建立了一、二、三级概率安全评价(PSA)分析程序;结合300MW核电厂二期工程(C-2)设计,对一、二级PSA技术进行研究及应用——包括始发事件分析、事件树分析、故障树分析、相关性分析、人员可靠性分析、数据分析、事件序列定量化、电厂损伤状态分析、事故进程和安全壳响应分析、源项分析、大量放射性早期释放频率(LERF)的计算和分析、不确定性分析、重要度和敏感性分析以及设计过程中的应用等。建造了C-2一、二级PSA模型,通过在C-2设计过程中基于PSA的发现进行了一些重要设计改进,如安注泵和喷淋泵的小流量回流管上隔离阀的设计改进;化容系统的往复式上充泵的设计改进;重要厂用水系统的设计改进等,得到C-2功率运行内部事件的堆芯损伤频率(CDF)为7.25×10-6/堆年,LERF定量化结果为3.24×10-7/堆年。
The software for Level 1, 2 and 3 probabilistic safety assessments （PSA） was developed based on the PSA code by the US Nuclear Regulatory Commission and independent research. It was applied to integrating the design of a 300 MW nuclear power plant, unit 2 （C-2）. It includes the analysis of initiating events, event trees, fault trees, dependency analysis, human reliability analysis, database analysis, event sequence quantification, plant damage state analysis, accident progression and containment response analysis, source term analysis, large early release frequency （LERF） analysis, uncertainty analysis, importance/sensitivity analysis, applications during design phase, etc. The model of Level 1 and 2 PSA was established for the C-2 unit. Several design improvements based on the PSA were implemented in the design, such as the isolation valves on the mini-flow line of the safety injection pump and spray pump, reciprocating charging pump in chemical and volume control system, essential service water system, etc. The unit＇s internal events at power generation were assessed as 7.25×10^-6/ry for core damage frequency （CDF） and 3.24×10^-7/ry for LERF. The C-2 PSA has not only justified the balance of its design, but also provided the probability assessment information for optimizing C-2 design and operation strategies, reducing the risk of severe accidents efficiently.
出处
《核技术》
CAS
CSCD
北大核心
2010年第2期87-91,共5页
Nuclear Techniques
