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Brochard, J.; Charras, T.; Ghoudi, M.
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] Modifications to a computer code for ductile fracture assessment of piping systems with postulated circumferential through-wall cracks under static or dynamic loading are very briefly described. The modifications extend the capabilities of the CASTEM2000 code to the determination of fracture parameters under creep conditions. The main advantage of the approach is that thermal loads can be evaluated as secondary stresses. The code is applicable to piping systems for which crack propagation predictions differ significantly depending on whether thermal stresses are considered as primary or secondary stresses
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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. 153; 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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