Stress corrosion crack growth rate of sensitized Type 304 stainless steel during high flux gamma-ray irradiation in 288{degrees}C water

Conference · Thu Dec 31 04:00:00 EST 1992

OSTI ID:48131

Nakata, K; Shimanuki, S; Anzai, H; Mabuchi, K; Fuse, M; Shigenaka, N ^[1]

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1. Hitachi Ltd., Ibaraki-ken (Japan)

Crack propagation tests in 288{degrees}C water were carried out using a 1/4 size compact tension specimen of sensitized Type 304 stainless steel (stress intensity; 25 MPa{radical}m) under {gamma}-ray irradiation (Co-60) with high fluxes of 1.3-2.3 x 10{sup 3} C/kgh. The intergranular SCC crack growth was slightly accelerated by {gamma}-ray irradiation were at most twice as large as that in unirradiated water. The crack growth rates increased almost linearly with increasing Na{sub 2}SO{sub 4} concentration in irradiated water containing more than 500 ppb dissolved oxygen (DO); in the 900 ppb DO condition, the crack growth rate of 2.6 x 10{sup 9} m/s in water containing 0.4 {mu}S/cm Na{sub 2}SO{sub 4} was about 5 times larger than that in high purity water of 0.07 {mu}S/cm. Although the NaNO{sub 3} addition also enhanced the crack propagation in 500 ppb DO water, NaNO{sub 3} was less harmful than Na{sub 2}SO{sub 4} in water. Hydrogen injection of 300-500 ppb into water was beneficial to prevent SCC crack propagation in 288{degrees}C water during {gamma}-ray irradiation.

• OSTI ID: 48131
• Report Number(s): CONF-910808--
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
CRACK PROPAGATION
DISSOLVED GASES
INTERGRANULAR CORROSION
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-304
STRESS CORROSION
WATER CHEMISTRY
WATER COOLED REACTORS