Published 1993 | Version v1
Book

Intergranular stress corrosion cracking of low alloy and carbon steels in high temperature pure water

  • 1. Toshiba Corporation, Yokohama (Japan)

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--.