原子能科学技术 ›› 2015, Vol. 49 ›› Issue (9): 1619-1623 .DOI: 10.7538/yzk.2015.49.09.1619

• 反应堆工程 • 上一篇    下一篇

田湾核电站反应堆压力容器承压热冲击分析

初起宝1;刘维平2;马静娴3;李海龙1,*   

  1. 1.环境保护部 核与辐射安全中心，北京100082；2.江苏核电有限公司，江苏 连云港222042；3.机械科学研究总院 核设备安全与可靠性中心，北京100044
  • 出版日期:2015-09-20 发布日期:2015-09-20

Pressurized Thermal Shock Analysis of Reactor Pressure Vessel of Tianwan Nuclear Power Plant

CHU Qi-bao1;LIU Wei-ping2;MA Jing-xian3;LI Hai-long1,*   

  1. 1.Nuclear and Radiation Safety Center, Ministry of Environmental Protection, Beijing 100082, China;2.Jiangsu Nuclear Power Co., Ltd., Lianyungang 222042, China;3.Nuclear Equipment Safety and Reliability Center, China Academy of Machinery Science and Technology, Beijing 100044, China
  • Online:2015-09-20 Published:2015-09-20

PDF

摘要：

反应堆压力容器（RPV）是核反应堆中不可替换的关键设备。田湾核电站在役前检查阶段，发现反应堆压力容器2#焊缝存在超标缺陷，2#焊缝处于堆芯筒体段，属强辐照区。为评价该缺陷的可接受性，采用有限元方法对反应堆压力容器2#焊缝进行了承压热冲击分析，在分析中考虑了小破口失水事故和安全阀误开启这两种最严酷工况。计算结果表明：有限元分析的结果与外国专家推荐方法的计算结果基本吻合，且田湾核电站反应堆压力容器2#焊缝寿期末的脆性转变温度小于最低容许脆性转变温度，能满足防脆断的设计要求。

关键词: 田湾核电站, 反应堆压力容器, 承压热冲击, 防脆断

Abstract:

The reactor pressure vessel (RPV) is an irreplaceable key equipment in nuclear reactor. It was found that 2# weld defects of RPV exceeded the standard in the Tianwan Nuclear Power Plant inspection stage. The 2# weld was located in the core barrel, which was strong radiation area. To evaluate the acceptability of defects, the pressurized thermal shock analysis was done for 2# weld of RPV using the finite element method, which included small break loss of coolant accident and PRZ-SV inadvertent opening. The calculation results show that the result of finite element analysis is coincided basically with results using foreign expert recommended method. The 2# weld of RPV, in which the brittle transition temperature of the final life is lower than that of the minimum allowable, can be satisfied with the requirement of resistance to brittle fracture.

Key words: Tianwan Nuclear Power Plant, reactor pressure vessel, pressurized thermal shock, resistance to brittle fracture