Published May 2004 | Version v1
Journal article

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

Optional Information

Notes
21 refs., 7 figs., 4 tabs.