轻水堆核电站奥氏体不锈钢铸件的热老化及其老化管理

留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名

邮箱

手机号码

标题

留言内容

验证码

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

1. Daya Bay Nuclear Power Operation and Management Co. Ltd., Shenzhen, Guangdong, 518124, China;
2. Suzhou Thermal Research Institute, Suzhou, Jiangsu, 215004, China

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。
- 奥氏体不锈钢铸件 /
- 热老化 /
- 老化管理 /
- 评估
Abstract: 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 components.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 plants in China.
- Cast austenitic stainless steel /
- Thermal aging /
- Aging management /
- Assessment