Published 1993 | Version v1
Book

Stress corrosion cracking of low steel weldments in LWR environments

  • 1. Technical Research Centre of Finland, Espoo (Finland)
  • 2. Metallurgy Laboratory, Espoo (Finland)

Description

Results obtained at VTT in the ICG-EAC Group bolt-loaded WOL specimen testing round robin for pressure vessel steel weldments in simulated PWR primary water (typical of Loviisa VVER-440 power plant) are presented. Two low alloy type A508 C1.2 steels were tested; one steel had a very low S-content (0.002% S) and the other steel had normal medium S-content (0.008/0.009% S). The low sulphur steel did not show any indication of stress corrosion crack growth, while in one specimen of normal A508 C1.2 steel minor crack extension (less than 1 mm) was locally observed at the precrack tip in the HAZ of the weldment. Crack extension was explained by a water chemistry transient in one phase of the test and the phase of cracking could be related to this occurrence by detailed fractographic examination. Because of difficulties in locating exactly the precrack tip in the HAZ of the weldment, it was observed in the end of the test that precrack tips in various specimens were located either in the weld metal or in the HAZ or in some cases also very close to the fusion line. Thus, this study was also testing the stress corrosion cracking susceptibilities of the various zones of the weldments of low alloy pressure vessel steel A508 C1.2. Stress corrosion crack extension in small amounts was observed only in one HAZ specimen of the normal medium S-content steel

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. 43-51.

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
25067156
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
CORROSION FATIGUE; CRACK PROPAGATION; LOW ALLOY STEELS; MATHEMATICAL MODELS; MECHANICAL PROPERTIES; REACTOR COMPONENTS; WELDED JOINTS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; FATIGUE; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; STEELS

Optional Information

Secondary number(s)
CONF-930825--.