第35卷第4期 2015年12月
核科学与工程
Nuclear Science and Engineering
基于PSA分析结果的AP1000
系统设计改进建议王成章，樊可，梁博，刘晶晶（中广核工程设计有限公司上海分公司，上海200241)
Vol.35No.4
Dec.2015
摘要：基于对AP1000一级概率安全分析(PSA)的结果，发现正常余热排出系统(RNS)的设计不足可能会导致安注管线破裂(SI-LB)始发事件对堆芯损坏频率(CDF)贡献较高。对正常余热排出系统进行适当的系统改进，采用概率安全分析的方法重新构建了改进后的RNS系统故障树及相关事件树模型，对 RNS系统可靠性进行分析，并对改进后核电厂CDF进行了计算，结果表明，RNS系统改进后可大大减
少安注管破裂始发事件导致的堆芯损坏，改进后电厂堆芯损坏额率(CDF)降低29.1%。关键调：概率安全评价；正常余热排出系统；堆芯损坏频率
中图分类号：TL32
文章标志码：A
文章编号：0258-0918(2015)04-0723-06
SuggestionforSystemImprovementoftheAPiooo
BasedonPSAresults
WANG Cheng-zhang,FAN Ke,LIANG Bo,LIU Jing-jing
(China nuclear design company shanghai branch, 200241, China)
Abstract:Based on the AP1oo0 level one Probabilistic Safety Assessment, the vulnerability of the normal residual heat removal system could lead to the high contribution of the initiating event of SI-LB. The Improvement of the normal residual heat removal system has been made. A fault tree and related event tree model of the RNS are rebuilt by the Probabilistic Safety Assessment methodology; the RNS system reliability and the contribution of the improvement on the CDF are analyzed.The results show that after the improvement of the RNS, the contribution of the SI-LB is greatly decreased and the core damage frequency is reduced by 29. 1%
Key words: Probabilistic Safety Assessment; The normal residual heat removal system: Core damage frequency
概率安全分析（ProbabilisticSafetyAnalysis，收稿日期：2014-04-27；修回日期：2015-07-09
PSA)是评价风险、认识风险、并帮助人们管理风
作者介：王成章（1982一），男，江苏句容人，工程师，硕士研究生，主要从事概事安全评价工作
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