Intergranular stress corrosion crack growth of sensitized type 304 stainless steel in a simulated boiling-water reactor environment

被引:16
|
作者
Kikuchi, E
Itow, M
Kuniya, J
Sakamoto, H
Yamamoto, M
Sudo, A
Suzuki, S
Kitamura, M
机构
[1] TOSHIBA CO LTD,NUCL ENGN LAB,ISOGO KU,YOKOHAMA,KANAGAWA 235,JAPAN
[2] TOSHIBA CO LTD,ISOGO ENGN CTR,ISOGO KU,YOKOHAMA,KANAGAWA 235,JAPAN
[3] HITACHI LTD,HITACHI WORKS,HITACHI,IBARAKI 317,JAPAN
[4] YOKYO ELECT POWER CO INC,POWER ENGN RES & DEV CTR,TSURUMI KU,YOKOHAMA,KANAGAWA 230,JAPAN
[5] TOKYO ELECT POWER CO INC,NUCL POWER STN,NARAHA,FUKUSHIMA 97906,JAPAN
关键词
boiling-water reactor; compact tension; constant load test; corrosion potential crack growth rate; hydrogen water chemistry; intergranular stress corrosion cracking; type 304 stainless steel;
D O I
10.5006/1.3280472
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Stress corrosion cracking (SCC) of type 304 (UNS S30400) stainless steel (SS) was studied using fracture mechanics-type standard compact tension (CT) specimens in simulated boiling-water reactor (BWR) environments at 288 degrees C. Tests were performed under constant loading. Crack lengths and crack growth rates (CGR) were determined by the reverse direct current (DC) potential drop method. Fractography was used to determine the mode of cracking and to confirm validity of the potential drop method for crack length determination Test environments were high-purity deionized water with < 10 ppb to 440 ppb dissolved oxygen (O-2) O ppb to 570 ppb hydrogen peroxide (H2O2), and 14 ppb to 150 ppb dissolved hydrogen (H-2). CGR were found to be 4.9 x 10(-8) mm/s to 3.0 x 10(-7) mm/s at an initial stress Intensity (K) of 31 MP root m (100 kgf/mm(1.5) in simulated normal water chemistry (NWC), However the CGR was < I x 10(-9) mm/s in simulated hydrogen water chemistry (HWC). CGR decreased with decreasing corrosion potential (E-corr). The critical potential below which SCC growth did not occur was < similar to -200 mV(SHE).
引用
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页码:306 / 311
页数:6
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