Studies of stress corrosion cracking in steels used for reactor pressure vessels
Conference
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OSTI ID:48093
- Babcock & Wilcox Co., Alliance, OH (United States)
- Electric Power Research Institute, Palo Alto, CA (United States)
This paper reviews the state of technology concerning stress corrosion crack growth in LWR environments and reports the results from a series of experiments that attempted to duplicate the results obtained from the literature. These experiments include one conducted in a steam environment representative of the condition in the upper head of a boiling-water reactor (BWR).
- OSTI ID:
- 48093
- Report Number(s):
- CONF-910808-; TRN: 95:011524
- Resource Relation:
- Conference: 5. international symposium on environmental degradation of materials in nuclear power systems - water reactors, Monterey, CA (United States), 25-29 Aug 1991; Other Information: PBD: 1992; Related Information: Is Part Of Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power systems - water reactors; PB: 995 p.
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:48093