轻水堆核电站奥氏体不锈钢铸件的热老化及其老化管理  

Thermal Aging and Aging Management of Cast Stainless Steel in LWR Nuclear Power Station

作　　者：刘鹏[1] 薛飞[2] 戴忠华[1] 陈世均[1] 朱文彬[1] 汪小龙[2] 遆文新[2] 

机构地区：[1]大亚湾核电运营管理有限责任公司,广东深圳518124 [2]苏州热工研究院,江苏苏州215004

出　　处：《核动力工程》2005年第S1期93-96,共4页Nuclear Power Engineering

摘　　要：在轻水堆核电站中,奥氏体不锈钢铸件(CASS)在运行温度下长期工作将面临热老化问题。本文对热老化的机理进行了描述,并针对核电站的热老化问题,给出了老化管理工作的主要步骤,即部件敏感性甄别、老化状态评估和ISI大纲更新;结合CASS热老化的老化管理实践,对我国核电站的热老化管理工作提出了建议。Austenitic Stainless Steel Castings in LWR nuclear power plants are susceptible to thermal aging at operating temperature.This article describes the mechanism of thermal aging for CASS compo-nents.It gives a general procedure for thermal aging management in nuclear power plants(three steps: susceptibility screening,assessment of degree of material embrittlement and ISI programme renew) on the basis of the aging management practices.Then it gives some advices about thermal aging management of nuclear power p...

关 键 词：奥氏体不锈钢铸件 热老化 老化管理 评估 

分 类 号：TL421[核科学技术—核技术及应用]