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

Book · Sun Dec 31 04:00:00 EST 1995

OSTI ID:203778

Kodama, Mitsuhiro; Katsura, Ryoei; Morisawa, Junichiro; Nishimura, Seiji ^[1]; Suzuki, Shunichi; Takamori, Kenro ^[2]; Shima, Seishi ^[3]; Kato, Takahiko ^[4]

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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

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.

• OSTI ID: 203778
• Report Number(s): CONF-950816--; ISBN 1-877914-95-9
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CRACK PROPAGATION
EXPERIMENTAL DATA
GAMMA RADIATION
HYDROGEN EMBRITTLEMENT
MITIGATION
PHYSICAL RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEEL-304L
WATER COOLED REACTORS