skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: IASCC susceptibility of irradiated austenitic stainless steel under very low dissolved oxygen

Abstract

Slow strain rate tests of Type 304 stainless steel (SS) irradiated to 1.3 {times} 10{sup 26} n/m{sup 2} (E>1MeV) were conducted in high-temperature water and argon gas environment to discuss irradiation-assisted stress corrosion cracking (IASCC) mechanism with respect to the dissolved oxygen (DO) effect. IASCC susceptibility of Type 304 SS decreased with decreasing DO. However, IASCC was not mitigated completely in the hydrogen injected water. And IG fracture was not observed in the case of argon gas environment. These results indicated that the high-temperature aqueous environment was an indispensable condition for the occurrence of IASCC. Moreover, lowering DO(<1ppb) did not necessarily eliminate IASCC susceptibility when austenitic stainless steel was irradiated to high neutron fluence. By considering H{sub 2}O{sub 2} formed by {gamma}-ray irradiation, IASCC at very low DO could not be explained by an active path corrosion model. At high DO, IASCG would be affected by the active path corrosion of radiation-induced chromium depletion. However, at very low DO, the possibility that IASCC would be affected by other mechanisms such as hydrogen embrittlement was suggested.

Authors:
; ; ;  [1]; ;  [2];  [3];  [4]
  1. Nippon Nuclear Fuel Development Co., Ltd., Ibaraki (Japan)
  2. Tokyo Electric Power Co. Inc., Yokohama (Japan). Materials Engineering Dept.
  3. Toshiba Corp., Yokohama (Japan). Nuclear Energy Division
  4. Hitachi Ltd., Ibaraki (Japan). Hitachi Works
Publication Date:
OSTI Identifier:
203778
Report Number(s):
CONF-950816-
ISBN 1-877914-95-9; TRN: 96:009744
Resource Type:
Book
Resource Relation:
Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 620 p.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; WATER COOLED REACTORS; REACTOR MATERIALS; STAINLESS STEEL-304L; PHYSICAL RADIATION EFFECTS; CRACK PROPAGATION; MITIGATION; GAMMA RADIATION; HYDROGEN EMBRITTLEMENT; EXPERIMENTAL DATA

Citation Formats

Kodama, Mitsuhiro, Katsura, Ryoei, Morisawa, Junichiro, Nishimura, Seiji, Suzuki, Shunichi, Takamori, Kenro, Shima, Seishi, and Kato, Takahiko. IASCC susceptibility of irradiated austenitic stainless steel under very low dissolved oxygen. United States: N. p., 1995. Web.
Kodama, Mitsuhiro, Katsura, Ryoei, Morisawa, Junichiro, Nishimura, Seiji, Suzuki, Shunichi, Takamori, Kenro, Shima, Seishi, & Kato, Takahiko. IASCC susceptibility of irradiated austenitic stainless steel under very low dissolved oxygen. United States.
Kodama, Mitsuhiro, Katsura, Ryoei, Morisawa, Junichiro, Nishimura, Seiji, Suzuki, Shunichi, Takamori, Kenro, Shima, Seishi, and Kato, Takahiko. Sun . "IASCC susceptibility of irradiated austenitic stainless steel under very low dissolved oxygen". United States.
@article{osti_203778,
title = {IASCC susceptibility of irradiated austenitic stainless steel under very low dissolved oxygen},
author = {Kodama, Mitsuhiro and Katsura, Ryoei and Morisawa, Junichiro and Nishimura, Seiji and Suzuki, Shunichi and Takamori, Kenro and Shima, Seishi and Kato, Takahiko},
abstractNote = {Slow strain rate tests of Type 304 stainless steel (SS) irradiated to 1.3 {times} 10{sup 26} n/m{sup 2} (E>1MeV) were conducted in high-temperature water and argon gas environment to discuss irradiation-assisted stress corrosion cracking (IASCC) mechanism with respect to the dissolved oxygen (DO) effect. IASCC susceptibility of Type 304 SS decreased with decreasing DO. However, IASCC was not mitigated completely in the hydrogen injected water. And IG fracture was not observed in the case of argon gas environment. These results indicated that the high-temperature aqueous environment was an indispensable condition for the occurrence of IASCC. Moreover, lowering DO(<1ppb) did not necessarily eliminate IASCC susceptibility when austenitic stainless steel was irradiated to high neutron fluence. By considering H{sub 2}O{sub 2} formed by {gamma}-ray irradiation, IASCC at very low DO could not be explained by an active path corrosion model. At high DO, IASCG would be affected by the active path corrosion of radiation-induced chromium depletion. However, at very low DO, the possibility that IASCC would be affected by other mechanisms such as hydrogen embrittlement was suggested.},
doi = {},
url = {https://www.osti.gov/biblio/203778}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {12}
}

Book:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this book.

Save / Share: