Severe accident sequence assessment for boiling water reactors: program overview

Conference · Wed Oct 01 04:00:00 EDT 1980

OSTI ID:6192378

Fontana, M. H.

The Severe Accident Sequence Assessment (SASA) Program was started at the Oak Ridge National Laboratory (ORNL) in June 1980. This report documents the initial planning, specification of objectives, potential uses of the results, plan of attack, and preliminary results. ORNL was assigned the Brown's Ferry Unit 1 Plant with the station blackout being the initial sequence set to be addressed. This set includes: (1) loss of offsite and onsite ac power with no coolant injection; and (2) loss of offsite and onsite ac power with high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) as long as dc power supply lasts. This report includes representative preliminary results for the former case.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USDOE; NRC
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6192378
• Report Number(s): CONF-801053--9; ON: TI85004738
• Country of Publication: United States
• Language: English

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ACCIDENTS
BWR TYPE REACTORS
COOLING SYSTEMS
ECCS
ELECTRIC POWER
EMERGENCY PLANS
ENERGY LOSSES
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FAULT TREE ANALYSIS
HIGH PRESSURE
HPCI
LOSSES
NATIONAL ORGANIZATIONS
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POWER
POWER LOSSES
RCIC SYSTEMS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS