Effect of the timing of vessel depressurization on a short-term station blackout in a BWR-4 performed with the MELCOR code
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6682722
- 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--
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Journal Name: Transactions of the American Nuclear Society; (United States) Vol. 66; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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·
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Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
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· Transactions of the American Nuclear Society
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLACKOUTS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DEPRESSURIZATION SYSTEMS
DESIGN BASIS ACCIDENTS
ELECTRIC POWER
ENRICHED URANIUM REACTORS
M CODES
PEACH BOTTOM-2 REACTOR
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POWER REACTORS
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REACTOR CORE DISRUPTION
REACTOR VESSELS
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THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLACKOUTS
BWR TYPE REACTORS
COMPUTER CODES
CONTAINERS
DEPRESSURIZATION SYSTEMS
DESIGN BASIS ACCIDENTS
ELECTRIC POWER
ENRICHED URANIUM REACTORS
M CODES
PEACH BOTTOM-2 REACTOR
POWER
POWER REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR VESSELS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS