The effect of dissolved oxygen on fatigue behavior of Alloy 690 steam generator tubes in borated and lithiated high temperature water

Author:

Tan Jibo,Wu Xinqiang,Han En-Hou,Liu Xiaoqiang,Xu Xuelian,Sun Haitao

Funder

Science and Technology Foundation of China

Special Funds for the Major State Basic Research Projects

Science and Technology Project of Yunnan Province

Yunnan Wenshan Dounan Manganese Industry Co., Ltd.

Institute of Metal Research (IMR)

Chinese Academy of Sciences (CAS)

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference44 articles.

1. Steam generator tube fatigue evaluation, Electric Power Research Institute, TR-107263 S415-02 S540-01, 1996.

2. The response of alloy 690 tubing in a pressurized water reactor environment;Young;Mater. Des.,2007

3. Effect of LWR Coolant Environments on Fatigue Life of Reactor Materials;Chopra,2007

4. Environmental fatigue evaluation method for nuclear power plants, JNES-SS-1005, 2011.

5. Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water;Tan;Corros. Sci.,2014

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