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Puls, M.P.; Wilkins, B.J.S.; Rigby, G.L.
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 probabilistic code for the prediction of the cumulative probability of pressure tube ruptures in CANDU type reactors is described. Ruptures are assumed to result from the axial growth by delayed hydride cracking. The BLOOM code models the major phenomena that affect crack length and critical crack length during the reactor sequence of events following the first indications of leakage. BLOOM can be used to develop unit-specific estimates of the actual probability of pressure rupture in operating CANDU reactors and supplement the existing leak before break analysis
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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. 733-740; 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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Conference
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