压水堆核电厂蒸汽发生器老化机理及其影响因素  

Ageing Mechanisms and Influencing Factors of Steam Generator in PWR Nuclear Power Plants

作　　者：龚嶷[1] 徐雪莲[1] 

机构地区：[1]上海核工程研究设计院上海市核电工程重点实验室,上海200233

出　　处：《腐蚀与防护》2014年第2期163-168,174,共7页Corrosion & Protection

基　　金：大型先进压水堆核电重大专项支撑项目(2010ZX06004-018)

摘　　要：蒸汽发生器是核电厂重要的核安全设备,其管束是最易发生失效的部位。基于国外核电厂实际运行经验与试验研究结果,概述了蒸汽发生器主要老化机理及其影响因素,明确了老化机理、老化缺陷、老化起因间的相互关系。该成可果为我国制定相应的压水堆核电厂蒸汽发生器老化管理大纲、实施定期安全审查,进而开展系统的寿命管理起参考作用。Steam generator is one of the major nuclear power plant components important to safety, and its tube bundle is also the weakest site susceptible to failures. Based on the previous worldwide operating histories and experimental research results, the ageing mechanisms and their influencing factors of steam generators are addressed, and the correlations among the ageing mechanisms, ageing defects and ageing causes are identified in this paper, which would have the reference value for the establishment of ageing management programs, implementation of periodic safety review （PSR） and the systematic life management of steam generators in pressurized water reactors in China.

关 键 词：压水堆(PWR) 蒸汽发生器 自然循环式 老化机理 传热管 

分 类 号：TG172[金属学及工艺—金属表面处理]