TRAC analysis of steam-generator overfill transients for TMI-1 [electronic resource].

Published:: Los Alamos, N.M. : Los Alamos National Laboratory, 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: Pages: 30 : digital, PDF file
Additional Creators:: Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

A reactor safety issue concerning the overfilling of once-through steam generators leading to combined primary/secondary blowdown has been raised recently. A series of six calculations, performed with the LWR best-estimate code, TRAC-PD2, on a Babcock and Wilcox Plant (TMI-1), was performed to investigate this safety issue. The base calculation assumed runaway main feedwater to one steam generator causing it to overfill and to break the main steam line. Four additional calculations build onto the base case with combinations of a pump-seal failure, a steam-generator tube rupture, and the pilot-operated relief valve not reseating. A sixth calculation involved only the rupture of a single steam-generator tube. The results of these analyses indicate that for the transients investigated, the emergency cooling system provided an adequate make-up coolant flow to mitigate the accidents.

Report Numbers:

E 1.99:la-ur-82-1786
E 1.99: conf-830103-14
conf-830103-14
la-ur-82-1786

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Note:

Published through SciTech Connect.
01/01/1983.
"la-ur-82-1786"
" conf-830103-14"
"DE82017333"
2. international topical meeting on nuclear thermalhydraulics, Santa Barbara, CA, USA, 11 Jan 1982.
Bassett, B.

Funding Information:

W-7405-ENG-36

View MARC record | catkey: 14370131