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AbstractAbstract
[en] The analysis of the experimental data of 304 stainless steel pipes using Zahoor and Kanninen's estimation scheme has shown that the J resistance curve of a circumferentially cracked pipe with a simulated internal surface crack around the remaining net section is much lower than the J resistance curve of pipes with a idealized through-wall crack (without a simulated internal surface crack). The implications of the low J at initiation and tearing modulus on the stability analysis of typical BWR piping systems are discussed on the condition that an internal circumferential surface crack is assumed to occur along with a circumferential through-wall crack due to stress corrosion. The results presented here show that the margin of safety is reduced and in some cases instability is predicted due to the low J resistance curve and tearing modulus
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Secondary Subject
Source
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 126-139; Aug 1984; p. 126-139; CSNI leak-before-break conference; Monterey, CA (USA); 1-2 Sep 1983; Available from NTIS, PC A24/MF A01 - GPO* $10.00 as TI84901888
Record Type
Report
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Conference
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ACCIDENTS, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, COOLING SYSTEMS, CORROSION, CORROSION RESISTANT ALLOYS, ENRICHED URANIUM REACTORS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INSTABILITY, IRON ALLOYS, IRON BASE ALLOYS, MECHANICAL PROPERTIES, MECHANICS, NICKEL ALLOYS, NUMERICAL SOLUTION, PLASMA INSTABILITY, PLASMA MACROINSTABILITIES, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, STAINLESS STEELS, STEELS, TENSILE PROPERTIES, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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