Fission product transport analysis in a loss of decay heat removal accident at Browns Ferry

Conference · Sat Dec 31 23:00:00 EST 1983

OSTI ID:6402592

Wichner, R P; Weber, C F; Hodge, S A; Beahm, E C; Wright, A L

This paper summarizes an analysis of the movement of noble gases, iodine, and cesium fission products within the Mark-I containment BWR reactor system represented by Browns Ferry Unit 1 during a postulated accident sequence initiated by a loss of decay heat removal (DHR) capability following a scram. The event analysis showed that this accident could be brought under control by various means, but the sequence with no operator action ultimately leads to containment (drywell) failure followed by loss of water from the reactor vessel, core degradation due to overheating, and reactor vessel failure with attendant movement of core debris onto the drywell floor.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6402592
• Report Number(s): CONF-8410142-85; ON: TI86002275
• Country of Publication: United States
• Language: English

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BROWNS FERRY-1 REACTOR
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ENRICHED URANIUM REACTORS
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FISSION PRODUCT RELEASE
MIXED SPECTRUM REACTORS
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RADIOACTIVITY TRANSPORT
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REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
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RHR SYSTEMS
SCRAM
SHUTDOWNS
WATER COOLED REACTORS
WATER MODERATED REACTORS