Role of radiation-induced grain boundary segregation in irradiation assisted stress corrosion cracking
- 1. Inst. of Nuclear Safety System, Inc., Mihama, Fukui (Japan)
- 2. Nippon Nuclear Fuel Development, Co., Ltd., Oarai, Ibaraki (Japan)
Description
Isolation of microstructural and microchemical effects on irradiation assisted stress corrosion cracking (IASCC) was attempted by means of low-dose high-temperature neutron irradiation in a material test reactor to get better under-standing on IASCC. Microstructure, grain boundary segregation, hardness and SCC susceptibility were examined on stainless steels irradiated to 0.8 dpa at around 673 K. The irradiation caused well-developed grain boundary segregation without notable hardening or microstructural changes. No IASCC was found in 593 K hydrogenated water where-as the steels were highly susceptible to IASCC in 561 K oxygenated water. The results suggest that grain boundary segregation, probably Cr depletion, is sufficient to cause IASCC in oxygenated water and that other radiation-induced changes such as microstructure and hardening are required for IASCC in hydrogenated water. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 41
- Journal Issue
- 5
- Journal Page Range
- p. 594-600
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35061474
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CRACKS; GRAIN BOUNDARIES; HARDNESS; INDUCTION; IRRADIATION; MATERIALS TESTING REACTORS; MICROSTRUCTURE; SEGREGATION; SENSITIVITY; STAINLESS STEELS; STRESS CORROSION
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MECHANICAL PROPERTIES; MICROSTRUCTURE; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 21 refs., 7 figs., 4 tabs.