二代改进型核电厂严重事故下一回路卸压时机敏感性研究  

Sensitivity Analysis on Time of Reactor Coolant System Depressurization under Severe Accident for Generation Ⅱ+ Nuclear Power Plants

作　　者：种毅敏[1] 杨志义[1] 石雪垚 张佳佳[1] 李春[1] 倪曼[1] 徐雨婷 

机构地区：[1]环境保护部核与辐射安全中心,北京100082 [2]中国核电工程有限公司,北京100840

出　　处：《核科学与工程》2015年第1期141-147,共7页Nuclear Science and Engineering

基　　金：环保公益性行业科研专项(201309054);哈尔滨工程大学专项科研基金项目(HEUFN1303)

摘　　要：一回路卸压是核电厂缓解严重事故的必要手段,也是严重事故管理导则(SAMG)的重要内容,国内核电厂严重事故管理中对一回路卸压的要求并不相同,本文基于典型二代改进型核电厂SAMG演练的场景,使用一体化计算程序MAAP4,对一回路卸压时机进行敏感性分析,比较不同卸压时机对缓解严重事故效果的影响,所给出的结论可为相同类型核电厂制定严重事故管理策略时提供参考。Reactor coolant system （RCS） depressurization is necessary measure for nuclear power plant to mitigate the severe accident, as well as a significant part of the severe accident management guidelines （SAMG）. Difference may exist on the time of RCS depressurization in different NPPs. In this paper, based on MAAP4, the sensitivity analysis of time to implement RCS depressurization is performed. A typical integrated computer program, and different effects on mitigation of severe accident are compared. The simulation scenario is typical drill situation of generation Ⅱ 4- NPPs, and conclusions can be reference for similar NPPs to implement severe accident management strategy.

关 键 词：二代加核电厂 严重事故管理 一回路卸压 敏感性分析 

分 类 号：TL364.4[核科学技术—核技术及应用]