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Mills, W.J.; James, L.A.; Blackburn, L.D.
Hanford Engineering Development Lab., Richland, WA (USA)1985
Hanford Engineering Development Lab., Richland, WA (USA)1985
AbstractAbstract
[en] PNC provided SUS 304 plate to be irradiated in FFTF at about 4000C to a target fluence of 5 x 1021 n/cm2 (E > 0.1 MeV). The actual irradiation included two basically different exposure levels to assure that information would be available for the exposure of interest. After irradiation, tensile properties, fatigue-crack growth rates and J-integral fracture toughness response were determined. These same properties were also measured for the unirradiated material so radiation damage effects could be characterized. This report presents the results of this program. It is expected that these results would be applicable for detailed fracture analysis of reactor components. Recent advances in elastic-plastic fracture mechanics enable reasonably accurate predictions of failure conditions for flawed stainless steel components. Extensive research has focused on the development of J-integral-based engineering approach for assessing the load carrying capacity of low-strength, high-toughness structural materials. Furthermore, Kanninen, et al., have demonstrated that J-integral concepts can accurately predict the fracture response for full-scale cracked structures manufactured from Type 304 stainless steel
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Aug 1985; 185 p; Available from NTIS, PC A09/MF A01; 1 as DE86013087; Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted.
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Report
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ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CONTAINERS, CORROSION RESISTANT ALLOYS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MATERIALS, MECHANICAL PROPERTIES, MECHANICS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, RADIATION EFFECTS, REACTORS, STAINLESS STEELS, STEELS, TESTING
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