蒸汽发生器传热管诱发破裂风险评估  

Risk Evaluation for Induced Steam Generator Tube Rupture

作　　者：杨健 朱文韬 

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《核动力工程》2017年第1期51-55,共5页Nuclear Power Engineering

摘　　要：蒸汽发生器传热管的诱发破裂是核电厂二级概率安全分析(PSA)中要重点评价的严重事故现象之一。首先识别引起该事故的关键因素,对此建立事故进程事件树(APET),并通过风险导向的事故分析方法(ROAAM),结合热工-水力计算和参数抽样,确定APET中重要现象节点的发生概率,定量评估堆芯损坏严重事故阶段诱发蒸汽发生器传热管破裂(SGTR)事故的发生频率和条件概率,并对降低SGTR风险的设计特征进行讨论。In the progression of a severe accident sequence, the induced rupture of SG tubes is of most concern in level 2 PSA. The key factors of these phenomena are identified firstly, and then modeled in the Accident Progression Event Tree （APET） by the Risk Oriented Accident Analysis Method （ROAAM）. The probabilities of important nodes in these event trees are determined by the combination of hydrogen-thermal analysis and parameter sample methods. Finally, the conditional probabilities and frequencies of induced SGTR during severe accident phase are calculated. The design characteristics for reducing the risk of induced SGTR are also discussed in this paper.

关 键 词：事故进程事件树(APET) 风险导向的事故分析方法(ROAAM) 概率安全分析(PSA) 严重事故管理导则(SAMG) 早期大量释放 

分 类 号：TL364.5[核科学技术—核技术及应用] TL364.4