Intergranular stress corrosion cracking of low alloy and carbon steels in high temperature pure water
Description
Stress corrosion cracking (SCC) behavior of low alloy steels (A508 and SNCM630) and a carbon steel (SGV480) in high temperature water has been examined with relation to the heat treatment condition, including a long time aging, and the mechanical properties. Intergranular stress corrosion cracking (IGSCC) as observed in the highly hardened specimens, and there was observed in the highly hardened specimens, and there was observed in the highly hardened specimens, and there was observed a close relationship between hardness and SCC susceptibility. From the engineering point of view, it was concluded that adequate SR (stress relief) or tempering heat treatment is necessary to avoid the IGSCC of the welded structures made of low alloy and carbon steels. A508 heat treated with specified quench and temper did not show the SCC susceptibility, even after aging 10000 hours at 350, 400 and 450 degrees C. Tensile properties corresponding to the critical hardness for SSC susceptibility coincided with the values at the 'necking point' in the true stress-strain curve. Ductile-brittle transition observed in the fracture toughness test also occurred at around the critical hardness for SCC susceptibility. Therefore, it was conjectured that the limitation of plasticity was an absolute cause for the SCC susceptibility of the steels
Additional details
Publishing Information
- Publisher
- Minerals, Metals ampersand Materials Society.
- Imprint Place
- Warrendale, PA (United States)
- Imprint Title
- Proceedings of the sixth international symposium on environmental degradation of materials in nuclear power systems - water reactors
- Imprint Pagination
- 963 p.
- Journal Page Range
- p. 53-58.
Conference
- Title
- water reactors.
- Acronym
- 6. international symposium on environmental degradation of materials in nuclear power systems
- Dates
- 1-5 Aug 1993.
- Place
- San Diego, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25067157
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; CRACK PROPAGATION; LOW ALLOY STEELS; REACTOR VESSELS; STRESS CORROSION; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CONTAINERS; CORROSION; IRON ALLOYS; IRON BASE ALLOYS; REACTORS; STEELS
Optional Information
- Secondary number(s)
- CONF-930825--.