Post-irradiation annealing effects of austenitic stainless steels in IASCC
Conference
·
OSTI ID:350096
- Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)
- Hitachi Ltd., Hitachi, Ibaraki (Japan)
- Toshiba Corp., Yokohama (Japan)
- Tokyo Electric Power Co., Ltd., Yokohama (Japan)
Post-irradiation annealing effects on the thermal sensitization and IASCC recovery for highly irradiated types 304 and 316L stainless steels were investigated using EPR and SSR tests. Irradiated type 316L stainless steel (neutron fluence: 8 x 10{sup 25} n/m{sup 2}, E > 1 MeV) was not sensitized and IGSCC susceptibility significantly was reduced to 7--0% at 400--700 C (x1h) from 23% at as-irradiated condition. Irradiated type 304 stainless steel (neutron fluence: 1.2 x 10{sup 26} n/m{sup 2}, E > 1MeV) was more easily sensitized than unirradiated material and IGSCC susceptibility was reduced to 62--45% at 400--500 C from 95% at the as-irradiated condition. These results on types 304 and 316L stainless steels indicated that the thermal healing technic enhanced IASCC recovery.
- OSTI ID:
- 350096
- Report Number(s):
- CONF-980316--
- Country of Publication:
- United States
- Language:
- English
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