堆内构件用不锈钢辐照加速应力腐蚀开裂研究进展

doi:10.3981/j.issn.1000-7857.2014.20.013

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摘要针对核电站堆内构件用不锈钢的辐照加速应力腐蚀开裂（IASCC）问题，分析了发生IASCC 的可能机制，论述了进行IASCC 模拟研究的方法，提出了缓解IASCC 的具体措施。辐照诱导偏析引起的晶界Cr 贫化、辐照硬化与辐照形变是发生IASCC 的可能机制；带电粒子辐照、敏化处理和多尺度模拟是反应堆堆内构件用不锈钢IASCC 研究的主要模拟方法；化学元素控制、微结构处理、应力水平控制与水化学成分控制是缓解不锈钢IASCC 的重要措施。

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	王荣山
	徐超亮
	黄平
	刘向兵
	陈明亚

关键词 ：堆内构件, 不锈钢, 辐照加速应力腐蚀开裂

Abstract：The mechanisms, simulation methods and mitigation measures of irradiation assisted stresscorrosion cracking (IASCC) in reactor internals stainless steels are discussed. The results indicate that the irradiation induced segregation, irradiation hardening and irradiation deformation are the mechanisms of IASCC, and the irradiation by charged particles, sensitized treatment and multi-scale simulation are the basic research methods. Based on the investigations of IASCC, the concentration control of chemical elements, microstructure changes, stress level control and water chemistry treatment are the main methods to mitigate IASCC.

Key words： reactor internals stainless steel irradiation assisted strain corrosion cracking

收稿日期: 2014-03-06

ZTFLH:

TL341

基金资助:国家高技术研究发展计划（863计划）项目（2012AA050901）；苏州市科技发展计划项目（SYG201254）

通讯作者: 徐超亮（通信作者），工程师，研究方向为核电关键部件材料老化管理，电子信箱：xuchaoliang@cgnpc.com.cn E-mail: xuchaoliang@cgnpc.com.cn

作者简介: 王荣山，博士研究生，研究方向为核电站延寿与关键部件老化管理，电子信箱：cntsail@126.com

引用本文:

王荣山, 徐超亮, 黄平, 刘向兵, 陈明亚. 堆内构件用不锈钢辐照加速应力腐蚀开裂研究进展[J]. 科技导报, 2014, 32(20): 79-83.
WANG Rongshan, XU Chaoliang, HUANG Ping, LIU Xiangbing, CHEN Mingya. Research Advances of Irradiation Assisted Stress Corrosion Cracking in Stainless Steels Used for Reactor Internals. journal1, 2014, 32(20): 79-83.

链接本文:

http://www.kjdb.org/CN/10.3981/j.issn.1000-7857.2014.20.013 或 http://www.kjdb.org/CN/Y2014/V32/I20/79

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