Severe accident sequences simulated at the Grand Gulf Nuclear Station

Journal Article · Wed Sep 01 00:00:00 EDT 1999 · Transactions of the American Nuclear Society

OSTI ID:678147

Carbajo, J J ^[1]

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1. Oak Ridge National Lab., TN (United States)

Different severe accident sequences employing the MELCOR code, version 1.8.4 QK, have been simulated at the Grand Gulf Nuclear Station (Grand Gulf). The postulated severe accidents simulated are two low-pressure, short-term, station blackouts; two unmitigated small-break (SB) loss-of-coolant accidents (LOCAs) (SBLOCAs); and one unmitigated large LOCA (LLOCA). The purpose of this study was to calculate best-estimate timings of events and source terms for a wide range of severe accidents and to compare the plant response to these accidents.

• OSTI ID: 678147
• Report Number(s): CONF-990605--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 80; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTERIZED SIMULATION
GRAND GULF-1 REACTOR
M CODES
REACTOR ACCIDENTS
SOURCE TERMS