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Aleev, A.; Petkevicius, K.; Senkus, V.
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] A number of cracks and damages of other sorts have been identified in the high-pressure parts at the Ignalina Nuclear Plant. They are caused by inadequate production- and repair technologies, as well as by thermal, chemical and mechanical processes of their performance. Several techniques are available as predictions of cracks and other defects of pressurized vessels. The choice of an experimental technique should be based on the level of its agreement with the actual processes
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Source
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. 593-600; Seminar on leak before break in reactor piping and vessels; Lyon (France); 9-11 Oct 1995; Also available from OSTI as TI97004806; NTIS; GPO
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Report
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Conference
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