Severe-accident-sequence assessment of hypothetical complete-station blackout at the Browns Ferry Nuclear Plant

Conference · Wed Dec 31 23:00:00 EST 1980

OSTI ID:5906910

Yue, D D; Condon, W A

An investigation has been made of various accident sequence which may occur following a complete loss of offsite and onsite ac power at a Boiling Water Reactor nuclear power plant. The investigation was performed for the Browns Ferry Nuclear Power Plant, and all accident sequences resulted in a hypothetical core meltdown. Detailed calculations were performed with the MARCH computer meltdown. Detailed calcuations were performed with the MARCH computer code containing a decay power calculation which was modified to include the actinides. This change has resulted in shortening the time before core uncovery by approx. 18%, and reducing the time before the start of core melting by approx. 26%. Following the hypothetical core meltdown accident, the drywell electric penetration assembly seals have been identified as the most likely leak pathway outside the containment. This potential mode of containment failure occurs at a pressure approx. 30% lower than that analyzed in the Reactor Safety Study.

• Research Organization: Oak Ridge National Lab., TN (USA); Tennessee Univ., Knoxville (USA). Dept. of Nuclear Engineering
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5906910
• Report Number(s): CONF-810905-9; ON: DE81904163
• Country of Publication: United States
• Language: English

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ACCIDENTS
BROWNS FERRY-3 REACTOR
BWR TYPE REACTORS
COMPUTER CALCULATIONS
ENERGY LOSSES
ENRICHED URANIUM REACTORS
LEAKS
LOSSES
MELTDOWN
MIXED SPECTRUM REACTORS
POWER LOSSES
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SEALS
WATER COOLED REACTORS
WATER MODERATED REACTORS