Studies of the steam generator degraded tubes behavior on BRUTUS test loop
Conference
·
OSTI ID:489362
- EDF/DER/MTC, Moret Sur Loing (France)
- EDF/EPN/DMAINT, Paris (France); and others
Studies for the evaluation of steam generator tube bundle cracks in PWR power plants are described. Global tests of crack leak rates and numerical calculations of crack opening area are discussed in some detail. A brief overview of thermohydraulic studies and the development of a mechanical probabilistic design code is also given. The COMPROMIS computer code was used in the studies to quantify the influence of in-service inspections and maintenance work on the risk of a steam generator tube rupture.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle, Columbus, OH (United States)
- OSTI ID:
- 489362
- Report Number(s):
- NUREG/CP--0155; CONF-9510432--; ON: TI97004806
- Country of Publication:
- United States
- Language:
- English
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