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AbstractAbstract
[en] Intergranular stress corrosion cracking (IGSCC) of sensitized Type 304 stainless steel (SS) has been a recurrent problem in the high-temperature water environment of boiling-water-reactors (BWRs) over the past two decades. The synergistic effects of environmental and material variables on stress corrosion cracking (SCC) of Type 304 SS were investigated at 2890C by means of constant-extension-rate-tensile (CERT) tests at a strain rate of 1 x 10-6/s. Correlations among environmental variables (dissolved oxygen and impurity concentrations, viz., H2SO4, steady-state open-circuit electro-chemical potential) and the SCC susceptibility parameters have been determined. The extensive results over a wide range of open-circuit corrosion potential conditions were analyzed by a model which accounts for the effects of environmental variables, microstructure (e.g., degree of sensitization) and strain rate. The results are consistent with a slip-dissolution mechanism for SCC. Furthermore, representation of the dependence of corrosion potential and average crack growth rate on the dissolved oxygen concentration of the water by a simple mathematical function, in conjunction with the theoretical model, enables predictions of both strain rate and environmental effects on the SCC susceptibility of sensitized Type 304 SS. 12 refs., 7 figs
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Jun 1985; 17 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 TI85014964
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Report
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Conference
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, COOLING SYSTEMS, CORROSION, CORROSION RESISTANT ALLOYS, ELECTRICAL PROPERTIES, ELEMENTS, ENRICHED URANIUM REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MATERIALS TESTING, NICKEL ALLOYS, NONMETALS, PHYSICAL PROPERTIES, POWER REACTORS, REACTOR COMPONENTS, REACTORS, STAINLESS STEELS, STEELS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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