Containment failure time and mode for a low-pressure short-term station blackout in a BWR-4 with Mark-I containment

Conference · Fri Jan 01 00:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7129195

Carbajo, J J; Greene, S R ^[1]

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

This study investigates containment failure time and mode for a low-pressure, short-term station blackout severe accident sequence in a boiling water reactor (BWR-4) with a Mark-I containment. The severe accident analysis code MELCOR, version 1.8.1, was used in these calculations. Other results using the MELCOR/CORBH package and the BWRSAR and CONTAIN codes are also presented and compared to the MELCOR results. The plant analyzed is the Peach Bottom atomic station, a BWR-4 with a Mark-I containment. The automatic depressurization system was used to depressurize the vessel in accordance with the Emergency Procedure Guidelines. Two different variations of the station blackout were studied: one with a dry cavity and the other with a flooded cavity. For the flooded cavity, it is assumed that a control rod drive (CRD) pump becomes operational after vessel failure, and it is used to pump water into the cavity.

• OSTI ID: 7129195
• Report Number(s): CONF-931160-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 69; Conference: American Nuclear Society (ANS) winter meeting, San Francisco, CA (United States), 14-18 Nov 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONTAINMENT
FAILURE MODE ANALYSIS
PEACH BOTTOM-2 REACTOR
B CODES
C CODES
DEPRESSURIZATION SYSTEMS
DESIGN BASIS ACCIDENTS
M CODES
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COMPUTER CODES
ENRICHED URANIUM REACTORS
POWER REACTORS
REACTOR ACCIDENTS
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WATER COOLED REACTORS
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Boiling Water Cooled