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AbstractAbstract
[en] The influence of different impurities, viz., oxyacids and several chloride salts, on the stress-corrosion-cracking (SCC) of sensitized Type 304 stainless steel (SS) was investigated in constant-extension-rate-tensile (CERT) tests in 2890C water at a low dissolved-oxygen concentration (<5 ppB). Cyclic loading experiments on fatigue precracked fracture-mechanics-type specimens of this material and Type 316NG were also performed at 2890C in low-oxygen environments with and without sulfate at low concentrations. In these experiments, the crack growth behavior of the materials was correlated with the type and concentration of the impurities and the electrochemical potentials of Type 304 SS and platinum electrodes in the simulated hydrogen-water chemistry environments. The information suggests that better characterization of water quality, through measurement of the concentrations of individual species (SO42-, NO3-, Cu2+, etc.) coupled with measurements of the corrosion and redox potentials at high temperatures will provide a viable means to monitor and ultimately improve the performance of BWR system materials
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Oct 1986; 10 p; Seminar on BWR corrosion, chemistry, and radiation control; Palo Alto, CA (USA); 10-12 Nov 1986; Available from NTIS, PC A02/MF A01; 1 as DE87004755; Portions of this document are illegible in microfiche products.
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ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHARGED PARTICLES, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION, CORROSION RESISTANT ALLOYS, DECOMPOSITION, ENRICHED URANIUM REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IONS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, POWER REACTORS, PYROLYSIS, REACTORS, STAINLESS STEELS, STEELS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WATER TREATMENT
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