先进压水堆核电厂主管道结构完整性的研究  

Study on Structural Integrity of Main Pipeline of Advanced PWR Nuclear Power Plant

作　　者：初起宝[1] 房永刚[1] 王庆[1] 南相辰 Chu Qibao Fang Yonggang Wang Qing Nan Xiangchen(Nuclear and Radiation Safety Center, Beijing, 100082, China)

机构地区：[1]环境保护部核与辐射安全中心,北京100082

出　　处：《核动力工程》2017年第5期45-48,共4页Nuclear Power Engineering

摘　　要：以某先进压水堆核电厂主管道为例,对核安全一级管道的结构完整性进行分析评价,并对根据规范设计的管道设计裕量进行了分析。管道结构完整性评价内容包括依据规范对管道强度进行评价、采用解析法求解管道温度场进行热棘轮评价、采用简化雨流法对管道进行疲劳寿命评价。计算结果表明,主管道最小壁厚减少至55 mm能够满足标准规范要求,但安全裕度较小,其中主管道支管位置的疲劳和热棘轮评价结果裕量最小。Taking a nuclear power plant as an example, the structural integrity of the nuclear safety class 1 pipe is analyzed and evaluated in this paper, and the design margin of the pipeline is analyzed according to the standard. The structural strength of pipeline is evaluated according to the standard, thermal ratchet is evaluated by analyzing the pipeline temperature theoretically, and the fatigue life of the pipeline is evaluated by using the simplified rain flow method. The results show that the minimum wall thickness of the main coolant pipe meets the requirements of the standards when reduced to 55mm, though the safety margin is small. The safety margin of fatigue and thermal ratcheting evaluation of branch is minimum.

关 键 词：主管道 壁厚减薄 结构完整性 疲劳寿命 热棘轮 

分 类 号：TL372[核科学技术—核技术及应用]