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作 者:王晗丁[1] 李琼哲 WANG Handing;LI Qiongzhe(Suzhou Nuclear Power Research Institute,Shenzhen of Guangdoug Prov.518000,China)
机构地区:[1]苏州热工研究院有限公司,广东深圳518000
出 处:《核科学与工程》2023年第2期377-382,共6页Nuclear Science and Engineering
摘 要:核电厂运行许可证延续必须考虑其延寿期内的核安全问题,确保核电机组在延期运行期间的核安全水平不低于原设计寿期内的核安全水平。可应用PSA技术对许可证延续期间的核电厂建立老化PSA模型,从而评估SSC老化对核电厂整体安全的影响,验证其仍可满足原设计标准。基于此提出了应用于核电厂老化PSA的SSC筛选分析方法,通过考虑趋势分析,老化失效模式与影响分析,风险重要度分析,在三种分析方法基础上建立核电厂SSC筛选的决策矩阵,为选择易老化且安全重要的部件建立了可行的方法。该项工作也为核电厂在许可证延续阶段的风险指引型管理奠定技术基础。We must ensure that the safety level of nuclear power plant during the extended operation period is not less than the original design safety level.The probabilistic safety assessment(PSA)technology can be used to establish aging PSA model for nuclear power plant during the license extension period,so as to evaluate the impact of SSC aging on the overall safety of nuclear power plant.Based on this,the SSC screening analysis method applied to aging PSA of nuclear power plant is proposed.By considering the aging trend analysis,aging failure mode and influence analysis(AFMEA),and risk importance analysis,the decision matrix is established,and a feasible method for selecting aging sensitive components to aging management is proposed.It also lays a technical foundation for risk-informed management of nuclear power plant in the license renewal stage.
分 类 号:TL48[核科学技术—核技术及应用]
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