期刊
出版社
ELSEVIER SCIENCE SA
DOI: 10.1016/j.msea.2014.05.069
关键词
Low cycle fatigue; PWR water; Alloy 690; Hydrogen; Dynamic strain aging
类别
资金
- Korea Hydro and Nuclear Power Co., Ltd.
- Nuclear Research & Development Program [20121610100040]
- KETEP-International Collaborative Energy Technology R&D Program of the MOTIE of the Republic of Korea [20128540010010]
- BK-Plus Program of the MSIP of the Republic of Korea
- Korea Evaluation Institute of Industrial Technology (KEIT) [20128540010010] Funding Source: Korea Institute of Science & Technology Information (KISTI), National Science & Technology Information Service (NTIS)
Low cycle fatigue (LCF) tests of Alloy 690 were performed in air and simulated PWR water under various loading conditions, and the results were analyzed to understand the LCF behavior of Alloy 690 in PWR water. The LCF life of Alloy 690 was shorter in PWR water than in air; however, the degree of reduction was less significant than for austenitic SSs. Through the tests and subsequent analysis, it was observed that dynamic strain aging (DSA) and hydrogen evolution by metal dissolution near the crack tip affect the fatigue crack growth behavior in PWR water. While DSA was observed, its effect on the LCF life was not evident. A hydrogen-induced dislocation structure was observed near the crack surface in TEM micrographs, indicating the operation of hydrogen-induced cracking (HIC) in PWR water. However, due to improved corrosion resistance, HIC was less operative for Alloy 690 than for austenitic SSs during the LCF test in PWR water. Consequently, the LCF life of Alloy 690 was longer than that of austenitic SSs in PWR water. (C) 2014 Elsevier B.V. All rights reserved.
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