Literature Survey on the Stress Corrosion Cracking of Low-Alloy Steels in High Temperature Water
Description
The present report is a summary of a literature survey on the stress corrosion cracking (SCC) behaviour/ mechanisms in low-alloy steels (LAS) in high-temperature water with special emphasis to primary-pressure-boundary components of boiling water reactors (BWR). A brief overview on the current state of knowledge concerning SCC of low-alloy reactor pressure vessel and piping steels under BWR conditions is given. After a short introduction on general aspects of SCC, the main influence parameter and available quantitative literature data concerning SCC of LAS in high-temperature water are discussed on a phenomenological basis followed by a summary of the most popular SCC models for this corrosion system. The BWR operating experience and service cracking incidents are discussed with respect to the existing laboratory data and background knowledge. Finally, the most important open questions and topics for further experimental investigations are outlined. (author)
Availability note (English)
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Additional details
Publishing Information
- Imprint Pagination
- 106 p.
- ISSN
- 1019-0643
- Report number
- PSI--02-06
INIS
- Country of Publication
- Switzerland
- Country of Input or Organization
- Switzerland
- INIS RN
- 33012833
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CORROSION FATIGUE; CRACK PROPAGATION; LOW ALLOY STEELS; NUMERICAL DATA; PRESSURE VESSELS; REVIEWS
- Descriptors DEC
- ALLOYS; CONTAINERS; DATA; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; FATIGUE; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 36 figs., 5 tabs., 218 refs.