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Collier, R.P.; Norris, D.M.
CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings1984
CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings1984
AbstractAbstract
[en] Experimental studies of critical two-phase water flow, through simulated and actual intergranular stress corrosion cracks, were performed to obtain data to evaluate a leak flow rate model and investigate acoustic transducer effectiveness in detecting and sizing leaks. The experimental program included a parametric study of the effects of crack geometry, fluid stagnation pressure and temperature, and crack surface roughness on leak flow rate. In addition, leak detection, location, and leak size estimation capabilities of several different acoustic transducers were evaluated as functions of leak rate and transducer position. This paper presents flow rate data for several different cracks and fluid conditions. It also presents the minimum flows rate detected with the acoustic sensors and a relationship between acoustic signal strength and leak flow rate
Primary Subject
Secondary Subject
Source
Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research; p. 273-299; Aug 1984; p. 273-299; 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
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACCIDENTS, ACOUSTIC TESTING, ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, COOLING SYSTEMS, CORROSION, CORROSION RESISTANT ALLOYS, DATA, ENRICHED URANIUM REACTORS, FLUID FLOW, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MATERIALS TESTING, MATHEMATICAL MODELS, NICKEL ALLOYS, NONDESTRUCTIVE TESTING, NUMERICAL DATA, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, STAINLESS STEELS, STEELS, TESTING, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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