Correlation between locally deformed structure and oxide film properties in austenitic stainless steel irradiated with neutrons
Source abstract
Abstract
Abstract To elucidate the mechanism of irradiation-assisted stress corrosion cracking (IASCC) in high-temperature water for neutron-irradiated austenitic stainless steels (SSs), the locally deformed structures, the oxide films formed on the deformed areas, and their correlation were investigated. Tensile specimens made of irradiated 316L SSs were strained 0.1%–2% at room temperature or at 563 K, and the surface structures and crystal misorientation among grains were evaluated. The strained specimens were immersed in high-temperature water, and the microstructures of the oxide films on the locally deformed areas were observed. The appearance of visible step structures on the specimens' surface depended on the neutron dose and the applied strain. The surface oxides were observed to be prone to increase in thickness around grain boundaries (GBs) with increasing neutron dose and increasing local strain at the GBs. No penetrative oxidation was observed along GBs or along surface steps.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Hydrogen embrittlement and corrosion behaviors in metals · Nuclear Materials and Properties · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (19)
Show source-provided references
1. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals10.1016/S0022-3115(99)00075-6 ↗
2. Recent developments in understanding irradiation assisted stress corrosion cracking
3. Stress corrosion cracking behavior of alloys in aggressive nuclear reactor core environments10.5006/1.3278331 ↗
4. Influence of localized deformation on irradiation-assisted stress corrosion cracking of proton-irradiated austenitic alloys
5. Deformation structure in 316 stainless steel irradiated in a PWR
6. Deformation structure in highly irradiated stainless steels10.1080/18811248.2008.9711437 ↗
7. Impact of localized deformation on IASCC in austenitic stainless steels10.1016/j.jnucmat.2010.10.087 ↗
8. An EBSD examination of SUS316 stainless steel irradiated to 73 dpa and deformed at 593 K10.1016/j.jnucmat.2010.12.301 ↗
9. Local strain distribution near grain boundaries under tensile stresses in highly irradiated SUS316 stainless steel10.1016/j.jnucmat.2012.08.038 ↗
10. Relationship between dislocation channeling and IASCC in neutron irradiated stainless steel
11. Progression of local strain states at dislocation channel-grain boundary intersections and their relation to IASCC in austenitic steels
12. Comparison of IGSCC crack-tip characteristics produced in BWR oxidizing water and BWR hydrogen water chemistry conditions
13. Correlation between oxide film and stress corrosion cracking susceptibility of surface cold worked L-grade stainless steels
14. Characterization of IASCC crack tip in highly irradiated stainless steels
15. Oxide film characterization along crack paths in stainless steel in aerated and deaerated water environments
16. Effects of locally deformed structure on oxide film properties in neutron-irradiated austenitic stainless steel
17. Crack growth behavior of neutron irradiated L-grade austenitic stainless steels in simulated BWR conditions
18. Analyses of surface oxides formed on irradiated stainless steels in simulated PWR primary water
19. Current understanding of radiation-induced degradation in light water reactor structural materials10.1080/00223131.2013.772448 ↗