Analysis of a SBLOCA initiated by an ATWS event [electronic resource].

Published: Upton, N.Y. : Brookhaven National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: Pages: 7 : digital, PDF file
Additional Creators: Brookhaven National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary

The response of a four-loop Westinghouse pressurized water reactor to SBLOCAs initiated as a result of an anticipated transient without scram (ATWS) has been analyzed using the RELAP5 computer code. The ATWS is initiated by a loss-of-feedwater, and the small breaks were due to either one or three stuck-open safety valves or reactor coolant pump seal failure. For the cases analyzed, the results show that a LOF-ATWS followed by a SBLOCA does not have more safety significance than that found when each accident is analyzed independently of one another.

Report Numbers

E 1.99:bnl-nureg-36009
E 1.99: conf-850646-1
conf-850646-1
bnl-nureg-36009

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Note

Published through SciTech Connect.
01/01/1985.
"bnl-nureg-36009"
" conf-850646-1"
"TI85007483"
2. international specialists meeting on small break LOCA analyses in LWRs, Pisa, Italy, 24 Jun 1985.
Shier, W.G.; Diamond, D.J.; Pu, J.

Funding Information

AC02-76CH00016

View MARC record | catkey: 14369135