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AbstractAbstract
[en] Fixed-load Mode I/Mode III comparative tests have been conducted on lightly sensitized (EPR = 2 C/cm2) Type 304 SS specimens in 2890C oxygenated water with other impurity additives. Substantial susceptibility to IGSCC was shown in Mode I but no conclusive evidence for SCC was found in Mode III. These results are consistent with a hydrogen embrittlement mechanism of crack advance, but electrochemical measurements seem to accord better with a slip-dissolution mechanism. Further studies are needed to clarify the operative mechanism(s)
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Jun 1985; 16 p; 2. international symposium on environmental degradation of materials in nuclear power systems--water reactors; Monterey, CA (USA); 9-12 Sep 1985; Available from NTIS, PC A02/MF A01 - GPO as TI85014965
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