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。
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.
出处
《科技导报》
CAS
CSCD
北大核心
2014年第20期79-83,共5页
Science & Technology Review
基金
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)
关键词
堆内构件
不锈钢
辐照加速应力腐蚀开裂
reactor internals
stainless steel
irradiation assisted strain corrosion cracking
