基于失效物理模型的聚变堆包层管道可靠性数据修正方法研究  

Research of Fusion Reactor Blanket Module Pipe Reliability Data Correction Method

作　　者：聂淼[1,2] 王芳[2] 王家群[2] 汪进[2] 袁润[2] 

机构地区：[1]中国科学技术大学,安徽合肥230027 [2]中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室,安徽合肥230031

出　　处：《核科学与工程》2017年第4期583-589,共7页Nuclear Science and Engineering

基　　金：中国科学院战略先导专项(XDA03040000);中国科学院信息化专项(XXH12504-1-09);国家ITER973专项(2015GB116000);中科院合肥物质科学研究院院长基金(YZJJ201327)等资助

摘　　要：由于聚变堆部件特殊的运行环境,部件可靠性数据极度匮乏,通常采用环境因子方法对现有可靠性数据进行修正,但现有可靠性数据修正模型未考虑解决高温模型不能适用的问题。本文提出了高温环境下的失效物理模型修正优化方法,提升了高温失效物理模型在极端环境下的适用范围和部件服役寿命修正精度,并基于失效物理模型修正方法开展了ITER中国氦冷固态包层氚提取系统(TES)管道可靠性数据修正研究,为TES系统可靠性分析提供了数据支持。Due to the special operation environment of fusion reactor components,component reliability data is extreme scarce.In general,the existing component reliability data was corrected based on environmental factor method.However existing correction model is not applicable any more under high temperature.In this the paper a variety of correction method of failure physics model with high temperature was proposed.The application range of the failure physical model and the correction precision of the operating life of the parts,in the condition of extreme environment,were improved effectively.And based on the existing system data correction function and general data,the reliability data correction was studied for the pipes of tritium extraction system（TES）of CN HCCB TBM,which provided data support for reliability analysis of fusion system.

关 键 词：可靠性数据 环境因子方法 管道失效率 失效物理模型 

分 类 号：TL69[核科学技术—核技术及应用]