Analysis of induced steam generator tube rupture using MAAP 4.0
- Dames & Moore, Westmont, IL (United States)
- Fauske & Assoc., Inc., Burr Ridge, IL (United States)
- Polestar Applied Technology, Los Altos, CA (United States)
The nuclear industry has initiated a program of Steam Generator Degradation Specific Management (SGDSM) to cope with the various types of corrosion that have been observed in pressurized water reactor (PWR) steam generators. In parallel, the U.S. Nuclear Regulatory Commission is promulgating revised rules on steam generator tube integrity. To support these efforts, the Electric Power Research Institute has sponsored calculations with the MAAP 4 code. The principal objective of these calculations is to estimate the peak temperatures experienced by the steam generator tubes during high-pressure severe accidents. These results are used to evaluate the potential for degraded tubes to leak or rupture. Attention was focused on station blackout (SBO) accidents with loss of turbine-driven auxiliary feedwater because these generally result in the greatest threat to the tubes.
- OSTI ID:
- 437029
- Report Number(s):
- CONF-9606116-; ISSN 0003-018X; TRN: 96:005275-0268
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 74; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996
- Country of Publication:
- United States
- Language:
- English
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