期刊
CORROSION SCIENCE
卷 108, 期 -, 页码 134-147出版社
PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.corsci.2016.03.001
关键词
Low alloy steel; Stress corrosion; Reactor conditions
资金
- Swiss Federal Nuclear Safety Inspectorate (ENSI)
- Swiss Federal Office of Energy
- Swissnuclear
- Swiss Federal Office for Education and Science
The effect of chloride on the stress corrosion crack (SCC) growth behaviour in low-alloy reactor pressure vessel steels was evaluated under simulated boiling water reactor conditions. In normal water chemistry environment, ppb-levels of chloride may result in fast SCC after rather short incubation periods of few hours. After moderate and short-term chloride transients, the SCC crack growth rates return to the same very low high-purity water values within few 100 h. Potential long-term (memory) effects on SCC crack growth cannot be excluded after severe and prolonged chloride transients. The chloride tolerance for SCC in hydrogen water chemistry environment is much higher. (C) 2016 Elsevier Ltd. All rights reserved.
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