Using MAAP 4.0 to determine risks from steam generator tube leaks or ruptures
- Polestar Applied Technology, Los Altos, CA (United States)
- Dames & Moore, Westmont, IL (United States)
As part of the Electric Power Research Institute (EPRI) program on steam generator degradation specific management (SGDSM), the nuclear industry is investigating the effects on plant risk of severe accidents involving steam generator tube leaks or ruptures. Such accidents fall into three classes: those caused by spontaneous, steam generator tube ruptures (SGTRs) that subsequently result in core damage; those caused by design-basis accidents that lead to induced tube ruptures and subsequent core damage; and those that progress to core damage, such as a station blackout (SBO), with subsequent induced tube leakage or rupture. In each case, the potential exists for a significant fraction of the fission products released from a damaged core to reach the environment through the leaking or ruptured tubes.
- OSTI ID:
- 437039
- Report Number(s):
- CONF-9606116-; ISSN 0003-018X; TRN: 96:005275-0278
- 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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