Advance Search
Volume 36 Issue 4
Feb.  2025
Turn off MathJax
Article Contents
Xiao Jun, Chen Luyao, Fu Zhenghong, Qiu Shaoyu, Chen Yong, Lin Zhenxia. Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors[J]. Nuclear Power Engineering, 2015, 36(4): 83-85. doi: 10.13832/j.jnpe.2015.04.0083
Citation: Xiao Jun, Chen Luyao, Fu Zhenghong, Qiu Shaoyu, Chen Yong, Lin Zhenxia. Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors[J]. Nuclear Power Engineering, 2015, 36(4): 83-85. doi: 10.13832/j.jnpe.2015.04.0083

Corrosion Fatigue Cracking Behavior of Inconel 690(TT) in Secondary Water of Pressurized Water Reactors

doi: 10.13832/j.jnpe.2015.04.0083
  • Received Date: 2014-10-22
  • Rev Recd Date: 2015-01-23
  • Available Online: 2025-02-15
  • Inconel 690(TT) is one of the key materials for tubes of steam generators for pressurized water reactors, where it is susceptible to corrosion fatigue cracking. In this paper, the corrosion fatigue cracking behavior of Inconel 690(TT) was investigated under small scale yielding conditions, in the simulated secondary water of pressurized water reactor. It was observed that the fatigue crack growth rate was accelerated by a maximum factor up to 3 in the simulated secondary water, comparing to that in room temperature air. In addition, it was found that the accelerating effect was influenced by out-of-plane cracking of corrosion fatigue cracks and also correlated with stress intensity factor range, maximum stress intensity factor and stress ratio.

     

  • loading
  • 加载中

Catalog

    通讯作者: 陈斌, bchen63@163.com
    • 1. 

      沈阳化工大学材料科学与工程学院 沈阳 110142

    1. 本站搜索
    2. 百度学术搜索
    3. 万方数据库搜索
    4. CNKI搜索

    Article Metrics

    Article views (27) PDF downloads(0) Cited by()
    Proportional views
    Related

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return