| 堆内构件用不锈钢辐照加速应力腐蚀开裂研究进展 |
| |
| 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(北京),2014,32(20):79-83. |
| |
| 作者姓名： | 王荣山 徐超亮 黄平 刘向兵 陈明亚 |
| |
| 作者单位： | 苏州热工研究院, 苏州215004 |
| |
| 基金项目： | 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) |
| |
| 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。
|
| 关 键 词： | 堆内构件 不锈钢 辐照加速应力腐蚀开裂 |
| 收稿时间： | 2014-03-06 |
Research Advances of Irradiation Assisted Stress Corrosion Cracking in Stainless Steels Used for Reactor Internals |
| |
| 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[J].Science & Technology Review,2014,32(20):79-83. |
| |
| Authors: | WANG Rongshan XU Chaoliang HUANG Ping LIU Xiangbing CHEN Mingya |
| |
| Institution: | Suzhou Nuclear Power Research Institute, Suzhou 215004, China |
| |
| 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. |
| |
| Keywords: | reactor internals stainless steel irradiation assisted strain corrosion cracking |
| 本文献已被 CNKI 等数据库收录！ |
| 点击此处可从《科技导报(北京)》浏览原始摘要信息 |
| 点击此处可从《科技导报(北京)》下载免费的PDF全文 |
|
