BWR 4/Mark I accident sequences assessment

Technical Report · Mon Nov 01 00:00:00 EST 1982

OSTI ID:6626962

Yue, D D; Cole, T E

This work uses the MARCH computer code to investigate the major events that may occur at a BWR 4/Mark I nuclear power plant following a number of postulated transients. These events are, in turn, correlated to the Nuclear Regulatory Commission Emergency Action Level Guidelines. The Browns Ferry Nuclear Plant Unit 1 was used as a model in this study. Under the assumptions used in this study, all accident sequences analyzed would eventually result in core-melt and containment breach unless the operator took corrective action. In each sequence, the effect of parameter variations on the accident progression has also been investigated. Results of this study show that in most core meltdown sequences overtemperature in the drywell electric penetration assembly (EPA) seals would be the dominant failure mode except for sequences TW, S/sub 2/I, and S/sub 2/J, in which there is a total loss of decay heat removal capability, with resultant higher pressure buildup in the containment. For the latter sequences, overpressurization would be the dominant containment failure mode.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6626962
• Report Number(s): NUREG/CR-2825; ORNL/TM-8148; ON: DE83003396
• Country of Publication: United States
• Language: English

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PRESSURE GRADIENTS
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COMPUTER CALCULATIONS
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