Effect of the timing of vessel depressurization on a short-term station blackout in a BWR-4 performed with the MELCOR code

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6682722

Carbajo, J J ^[1]

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

This study evaluates the effect that the timing of vessel depressurization has in the progression of a short-term station blackout accident in a boiling water reactor (BWR)-4. This study was performed with the MELCOR (version 1.8.1) severe-accident code. A similar study was previously completed at Oak Ridge National Laboratory (ORNL) using different computer codes. The purpose of this study is to confirm and expand on the previous study and investigate the applicability of MELCOR for severe-accident management analysis.

• OSTI ID: 6682722
• Report Number(s): CONF-921102-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; 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
BWR TYPE REACTORS
REACTOR VESSELS
DESIGN BASIS ACCIDENTS
M CODES
BLACKOUTS
DEPRESSURIZATION SYSTEMS
ELECTRIC POWER
PEACH BOTTOM-2 REACTOR
REACTOR CORE DISRUPTION
ACCIDENTS
COMPUTER CODES
CONTAINERS
ENRICHED URANIUM REACTORS
POWER
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled