Crack initiation mechanisms in IASCC of stainless steel alloys
- Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering
- GE Corporate Research and Development Labs., Schenectady, NY (United States)
An abnormally high oxygen concentration was recently discovered in a high purity stainless steel alloy widely used in IASCC studies. This led to an investigation into the role of oxygen on the initiation of intergranular cracking in irradiated samples in high temperature water. The concentration of oxygen in the alloys correlated with the number of cracks initiated in the proton irradiated region of samples strained in water containing 0.5 {micro}S/cm H{sub 2}SO{sub 4} at 288 C. This suggests that the presence of oxygen, in the form of spinel oxide particles, can lead to a substantial increase in the likelihood of crack initiation. This effect is only observed in irradiated samples strained in water, not in either unirradiated (non-sensitized) samples strained in water or irradiated samples strained in argon This paper examines the possible role of oxides in promoting crack initiation and the implications for IASCC.
- DOE Contract Number:
- FG02-93ER12130
- OSTI ID:
- 203777
- Report Number(s):
- CONF-950816-; ISBN 1-877914-95-9; TRN: 96:009743
- Resource Relation:
- Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 620 p.
- Country of Publication:
- United States
- Language:
- English
Similar Records
Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals.
Environmentally assisted cracking in light water reactors.