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Title: Pre-immersion effect on IASCC susceptibility in austenitic stainless steel

Abstract

Irradiation assisted stress corrosion cracking (IASCC) is now recognized as one of the major engineering concerns for extending the operating life of light water reactors (LWRs). IASCC appears in the form of intergranular stress corrosion cracking (IGSCC) and the threshold fluence level has been reported to be about 5 {times} 10 {sup 24}n/m{sup 2} (E>1MeV) in austenitic stainless steels such as types 304 and 316 SSs. In order to investigate the effect of oxide film on the initiation of irradiation assisted stress corrosion (IASCC), UCL (uniaxial constant load) tests of highly irradiated type 304 stainless steel (neutron fluence: 1.4 {times} 10{sup 26}n/m{sup 2}, E > 1MeV) with oxide film by pre-immersion were conducted in high temperature oxygenated pure water. IASCC susceptibilities were not observed even over the IASCC threshold stress level at 463--523 MPa during 2,000 hour tests. Analysis of TTF (times to failure) results in polished specimen of highly irradiated steels also supported the idea that the surface oxide film on irradiated specimens would affect the IASCC initiation mechanism, but not for IGSCC in unirradiated sensitized stainless steel. The mechanism of IASCC behavior was discussed from the viewpoint of the relationship between chromium depletion at a grain boundary andmore » the surface oxide film.« less

Authors:
; ;  [1]
  1. Nippon Nuclear Fuel Development Co., Ltd., Ibaraki (Japan)
Publication Date:
OSTI Identifier:
99569
Report Number(s):
CONF-950304-
TRN: 95:019177
Resource Type:
Book
Resource Relation:
Conference: Corrosion `95: National Association of Corrosion Engineers (NACE) international annual conference and corrosion show, Orlando, FL (United States), 26-31 Mar 1995; Other Information: PBD: 1995; Related Information: Is Part Of Corrosion/95 conference papers; PB: 5788 p.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; STAINLESS STEEL-304; PHYSICAL RADIATION EFFECTS; INTERGRANULAR CORROSION; STRESS CORROSION; CRACK PROPAGATION; WATER COOLED REACTORS; REACTOR MATERIALS; EXPERIMENTAL DATA; SERVICE LIFE

Citation Formats

Katsura, R, Morisawa, J, and Nishimura, S. Pre-immersion effect on IASCC susceptibility in austenitic stainless steel. United States: N. p., 1995. Web.
Katsura, R, Morisawa, J, & Nishimura, S. Pre-immersion effect on IASCC susceptibility in austenitic stainless steel. United States.
Katsura, R, Morisawa, J, and Nishimura, S. Fri . "Pre-immersion effect on IASCC susceptibility in austenitic stainless steel". United States.
@article{osti_99569,
title = {Pre-immersion effect on IASCC susceptibility in austenitic stainless steel},
author = {Katsura, R and Morisawa, J and Nishimura, S},
abstractNote = {Irradiation assisted stress corrosion cracking (IASCC) is now recognized as one of the major engineering concerns for extending the operating life of light water reactors (LWRs). IASCC appears in the form of intergranular stress corrosion cracking (IGSCC) and the threshold fluence level has been reported to be about 5 {times} 10 {sup 24}n/m{sup 2} (E>1MeV) in austenitic stainless steels such as types 304 and 316 SSs. In order to investigate the effect of oxide film on the initiation of irradiation assisted stress corrosion (IASCC), UCL (uniaxial constant load) tests of highly irradiated type 304 stainless steel (neutron fluence: 1.4 {times} 10{sup 26}n/m{sup 2}, E > 1MeV) with oxide film by pre-immersion were conducted in high temperature oxygenated pure water. IASCC susceptibilities were not observed even over the IASCC threshold stress level at 463--523 MPa during 2,000 hour tests. Analysis of TTF (times to failure) results in polished specimen of highly irradiated steels also supported the idea that the surface oxide film on irradiated specimens would affect the IASCC initiation mechanism, but not for IGSCC in unirradiated sensitized stainless steel. The mechanism of IASCC behavior was discussed from the viewpoint of the relationship between chromium depletion at a grain boundary and the surface oxide film.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {9}
}

Book:
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