Using MAAP 4.0 to determine risks from steam generator tube leaks or ruptures

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:437039

Fuller, E L ^[1]; Kenton, M A ^[2]

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1. Polestar Applied Technology, Los Altos, CA (United States)
2. 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--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN TANSAO; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
DESIGN BASIS ACCIDENTS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
LEAKS
M CODES
REACTOR ACCIDENTS
RISK ASSESSMENT
RUPTURES
SOURCE TERMS
STEAM GENERATORS
TUBES