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Hale, D.A.; Yuen, J.L.; Gerber, T.L.
General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div1978
General Electric Co., San Jose, CA (USA). Nuclear Energy Engineering Div1978
AbstractAbstract
[en] This report summarizes results of an experimental testing program focused on establishing the fatigue crack growth behavior of several commercial pressure vessel and piping steels typically used in light water reactors. Testing was done in a simulated boiling water reactor (BWR) primary water environment (1230 psig, 5500F demineralized water). The data obtained were analyzed using linear elastic fracture mechanics principles and, in the case of the reactor pressure vessel alloy steel, compared to existing ASME design codes. The results show that crack growth rates are increased in this BWR water environment by decreasing the frequency of cyclic loading or increasing the mean load present during the load cycle. However, in the case of the pressure vessel alloy steel, these effects are moderated by transverse secondary microcracking, which is a manifestation of a crack tip chemistry interaction for this environment/material pair. This behavior is consistent with previous GE experience with in-service cracking in pressure vessel components, wherein analytic projections of cracking rates always tend to overpredict crack depths when compared to actual field observations. The results for the Type-304 stainless steel and the Inconel 600 establish threshold values on cyclic loading frequency for intergranular stress corrosion cracking behavior in these two material/environment pairs
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Source
Aug 1978; 87 p; GEAP--24098; Available from NTIS., PC A05/MF A01
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Report
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ALLOYS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, CONTAINERS, COOLING SYSTEMS, CORROSION, CORROSION RESISTANT ALLOYS, HEAT RESISTING ALLOYS, INCONEL ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, MECHANICAL PROPERTIES, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIOBIUM ALLOYS, REACTOR COMPONENTS, REACTORS, STAINLESS STEELS, STEELS, TESTING, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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