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Title: Post-irradiation annealing effects of austenitic stainless steels in IASCC

Abstract

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.

Authors:
; ;  [1]; ;  [2]; ;  [3];  [4]
  1. Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)
  2. Hitachi Ltd., Hitachi, Ibaraki (Japan)
  3. Toshiba Corp., Yokohama (Japan)
  4. Tokyo Electric Power Co., Ltd., Yokohama (Japan)
Publication Date:
OSTI Identifier:
350096
Report Number(s):
CONF-980316-
TRN: IM9925%%444
Resource Type:
Conference
Resource Relation:
Conference: Corrosion `98, San Diego, CA (United States), 22-27 Mar 1998; Other Information: PBD: 1998; Related Information: Is Part Of Corrosion `98: 53. annual conference and exposition, proceedings; PB: [6600] p.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; WATER COOLED REACTORS; PHYSICAL RADIATION EFFECTS; STAINLESS STEEL-304; STAINLESS STEEL-316L; ANNEALING; STRESS CORROSION; CRACK PROPAGATION

Citation Formats

Katsura, Ryoei, Ishiyama, Yoshihide, Yokota, Norikatu, Kato, Takahiko, Nakata, Kiyotomo, Fukuya, Kouji, Sakamoto, Hiroshi, and Asano, Kyoichi. Post-irradiation annealing effects of austenitic stainless steels in IASCC. United States: N. p., 1998. Web.
Katsura, Ryoei, Ishiyama, Yoshihide, Yokota, Norikatu, Kato, Takahiko, Nakata, Kiyotomo, Fukuya, Kouji, Sakamoto, Hiroshi, & Asano, Kyoichi. Post-irradiation annealing effects of austenitic stainless steels in IASCC. United States.
Katsura, Ryoei, Ishiyama, Yoshihide, Yokota, Norikatu, Kato, Takahiko, Nakata, Kiyotomo, Fukuya, Kouji, Sakamoto, Hiroshi, and Asano, Kyoichi. Thu . "Post-irradiation annealing effects of austenitic stainless steels in IASCC". United States.
@article{osti_350096,
title = {Post-irradiation annealing effects of austenitic stainless steels in IASCC},
author = {Katsura, Ryoei and Ishiyama, Yoshihide and Yokota, Norikatu and Kato, Takahiko and Nakata, Kiyotomo and Fukuya, Kouji and Sakamoto, Hiroshi and Asano, Kyoichi},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/350096}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1998},
month = {12}
}

Conference:
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