Published 1974
| Version v1
Book
Stress corrosion failure of stainless steel components in a BWR and the effect of cyclic loading on the crack propagation
Description
Two types of problems originated from the stress corrosion cracking (SCC) of the stainless steel components are described. In both cases quantitative estimation of crack growth as functions of either time or number of operation cycles became of significant concern for the rest of life. The cracks in the weld overlay of the RPV liner were suspected to work as the stress raisers, when fatigue of the vessel in the corrosive aqueous environment was considered. More typical stress corrosion cracks around the weld joints became an alternative subject of study. A series of laboratory experiments on the effect of simulated reactor environment on the rate of crack growth under alternated stresses were conducted. 15 references
Additional details
Publishing Information
- Publisher
- Electrochemical Society, Inc.
- Imprint Place
- Princeton, NJ
- Imprint Title
- Corrosion problems in energy conversion and generation
- Imprint Pagination
- p. 346-358.
Conference
- Title
- Proceedings of the symposium on corrosion problems in energy conversion and generation.
- Dates
- 15 Oct 1974.
- Place
- New York, New York, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 7244990
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; FATIGUE; POWER TRANSMISSION; PRIMARY COOLANT CIRCUITS; REACTOR OPERATION; STAINLESS STEELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; OPERATION; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:See CONF-7410138--.