Severe accident sequences analyzed for a two-loop PWR

Journal Article · Sun Nov 30 23:00:00 EST 1997 · Transactions of the American Nuclear Society

OSTI ID:552510

Carbajo, J J ^[1]

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

Different severe accident sequences have been analyzed for a two-loop Westinghouse pressurized water reactor (PWR) using the MELCOR code, version 1.8.4. The purpose of this study was to calculate source terms and the timing of events for severe accident sequences at this type of PWR to be used in the HAS-CAL code .The results calculated by MELCOR have been compared to results from the individual plant examination (IPE) of the Kewaunee nuclear power plant, also a two-loop Westinghouse PWR. The results of the Kewaunee IPE were obtained with the severe accident code MAAP.

• OSTI ID: 552510
• Report Number(s): CONF-971125--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; 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
LOSS OF COOLANT
M CODES
PWR TYPE REACTORS
REACTOR ACCIDENTS
SOURCE TERMS