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Failure modes of alternate containment designs following postulated core meltdown

Technical Report ·
OSTI ID:7300223
The containment response to a postulated core meltdown accident in a PWR Ice Condenser Containment and a BWR Mark III Containment was examined to see if the WASH-1400 containment failure mode judgment for the Surry large, dry containment and the Peach Bottom Mark I containment are likely to be appropriate for ice-condenser and Mark III plant designs. Using event tree methodology, various accident sequences are identified for the reactor cores in these containment designs. Several of these accident sequences which represent the most adverse consequences to public safety are studied in depth. The PWR representative event is a large cold leg break accompanied by a loss of all electric power while the BWR representative event is a recirculation line break without adequate core cooling function. Two containment event paths are studied for each of these two cases depending on whether containment vapor suppression function is available or not. Both the core and the containment pressure and temperature response to the accident events are computed for the four-time intervals which characterize blowdown of the pipe break, core melt, vessel melt-through, and containment foundation penetration. The calculations are based on a best estimate of the most probable sequence.
Research Organization:
California Univ., Los Angeles (USA). School of Engineering and Applied Science
OSTI ID:
7300223
Report Number(s):
PB-261890; UCLA-ENG-7661
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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ACCIDENTS
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BWR TYPE REACTORS
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FAILURE MODE ANALYSIS
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PRESSURE GRADIENTS
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TEMPERATURE GRADIENTS
TIME DEPENDENCE
VAPOR CONDENSERS
WATER COOLED REACTORS
WATER MODERATED REACTORS