ENVIRONMENTAL FATIGUE OF METALLIC MATERIALS IN NUCLEAR POWER PLANTS - A REVIEW OF KOREAN TEST PROGRAMS

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Environmental fatigue of the metallic components in light water reactors has been the subject of extensive research and regulatory interest in Korea and abroad. Especially, it was one of the key domestic issues for the license renewal of operating reactors and licensing of advanced reactors during the early 2000s. To deal with the environmental fatigue issue domestically, a systematic test program has been initiated and is still underway. The materials tested were SA508 Gr.1a low alloy steels, 316LN stainless steels, cast stainless steels, and an Alloy 690 and 52M weld. Through tests and subsequent analysis, the mechanisms of reduced low cycle fatigue life have been investigated for those alloys. In addition, the effects of temperature, dissolved oxygen level, and dissolved hydrogen level on low cycle fatigue behaviors have been investigated. In this paper, the test results and key analysis results are briefly summarized. Finally, an on-going test program for hot-bending of 347 stainless steel is introduced.
Publisher
KOREAN NUCLEAR SOC
Issue Date
2013-12
Language
English
Article Type
Article
Keywords

LOW-CYCLE FATIGUE; AUSTENITIC STAINLESS-STEEL; LOW-ALLOY STEEL; DEOXYGENATED WATER; CRACK-GROWTH; DEGREES-C; 310-DEGREES-C; DEFORMATION; BEHAVIORS; HYDROGEN

Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.45, no.7, pp.929 - 940

ISSN
1738-5733
DOI
10.5516/NET.07.2013.040
URI
http://hdl.handle.net/10203/187124
Appears in Collection
NE-Journal Papers(저널논문)
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