Radiation hardening effects on localized deformation and stress corrosion cracking of stainless steels
- Pacific Northwest Lab., Richland, WA (United States)
- Michigan Univ., Ann Arbor, MI (United States)
Radiation hardening in austenitic stainless steels modifies deformation characteristics and correlate well with increased susceptibility to intergranular stress corrosion cracking (IGSCC). Available data on neutron-irradiated materials have been analyzed and correlations developed between fluence, yield strength, and cracking susceptibility in high-temperature water environments. Large heat-to-heat differences in critical fluence (0.2 to 2.5 {times} 10{sup 21} n/cm{sup 2}) for IGSCC are documented. In many cases, this variability is consistent with yield strength differences among irradiated materials. IGSCC correlates better to yield strength than to fluence for most heats suggesting a possible role of radiation-induced hardening (and microstructure) on cracking. Microstructural evolution during proton and heavy-ion irradiation has been characterized in low-carbon 302SSs. Hardening results from dislocation loops. SEM and TEM are used to examine dose, strain, and temperature effects on deformation. This hardened microstructure produces inhomogeneous planar deformation within the matrix. Regularly spaced steps are created at the surface during deformation which increase in number with increasing macroscopic strain. Twinning is the dominant deformation mechanism at low temperature, while dislocation channeling is observed at 288C. Deformation characteristics are discussed in terms of potential impact on IGSCC.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830; FG02-93ER12130
- OSTI ID:
- 10108251
- Report Number(s):
- PNL-SA-21725; CONF-930825-14; ON: DE94004308; BR: KC0501000; TRN: 94:000925
- Resource Relation:
- Conference: 6. international symposium on environmental degradation of materials in nuclear power systems: water reactors,San Diego, CA (United States),1-5 Aug 1993; Other Information: PBD: Aug 1993
- Country of Publication:
- United States
- Language:
- English
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