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Isozaki, Toshikuni; Shibata, Katsuyuki.
Proceedings of the seminar on leak before break in reactor piping and vessels1997
Proceedings of the seminar on leak before break in reactor piping and vessels1997
AbstractAbstract
[en] Experimental and computed results applicable to Leak Before Break analysis are presented. The specific area of investigation is the effect of the temperature distribution changes due to wetting of the test pipe near the crack on the increase in the crack opening area and leak rate. Two 12-inch straight pipes subjected to both internal pressure and thermal load, but not to bending load, are modelled. The leak rate was found to be very susceptible to the metal temperature of the piping. In leak rate tests, therefore, it is recommended that temperature distribution be measured precisely for a wide area
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Faidy, C. (ed.) (Electricite de France, Villeurbanne (France)); Gilles, P. (ed.) (Framatome, Paris (France)); Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle, Columbus, OH (United States); 773 p; Apr 1997; p. 325-334; Seminar on leak before break in reactor piping and vessels; Lyon (France); 9-11 Oct 1995; Also available from OSTI as TI97004806; NTIS; GPO
Record Type
Report
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Conference
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ALLOYS, CARBON ADDITIONS, COOLING SYSTEMS, ENRICHED URANIUM REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MECHANICS, POWER REACTORS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, STEELS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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