Contain calculations of debris conditions adjacent to the BWR Mark I drywell shell during the later phases of a severe accident
Copyright policy )Contain calculations of debris conditions adjacent to the BWR Mark I drywell shell during the later phases of a severe accident
Abstract Best estimate CONTAIN calculations have recently been performed by the BWR Severe Accident Technology (BWRSAT) Program at Oak Ridge National Laboratory to predict the primary containment response during the later phases of an unmitigated low-pressure Short Term Station Blackout at the Peach Bottom Atomic Power Station. Debris pour conditions leaving the failed reactor vessel are taken from the results of best estimate BWRSAR analyses that are based upon an assumed metallic debris melting temperature of 2750°F (1783 K) and an oxide debris melting temperature of 4350°F (2672 K). COINTAIN analyses were performed for the debris/concrete interaction occurring without consideration of the possible existence of an overlying pool of water. Results indicate failure of the drywell head seals due to the extremely hot atmospheric conditions extant in the drywell. The maximum calculated temperature of the debris adjacent to the drywell shell is less than the melting temperature of the shell, yet the sustained temperatures may be sufficient to induce primary containment pressure boundary failure by the mechanism of creep-rupture. It is also predicted that a significant portion of the reactor pedestal wall is ablated during the period of the calculation. Nevertheless, the calculated results are recognized to be influenced by large modeling uncertainties. Several deficiencies in the application of the CORCON module within the CONTAIN code to BWR severe accident sequences are identified and discussed.
- Oak Ridge National Laboratory United States
- Oak Ridge National Laboratory United States
- University of North Texas United States
- University of North Texas United States
Blackouts, Enriched Uranium Reactors, Helium Cooled Reactors, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Hydraulics, 990220 -- Computers, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Peach Bottom-3 Reactor, Mechanics, Reactor Accidents, Gas Cooled Reactors, C Codes, Corium, Light-Water Moderated, 22 General Studies Of Nuclear Reactors, Reactor Safety, Seals, Computer Codes, Computing, Containment, Thermal Reactors, Heat Transfer, Bwr Type Reactors, Reactors, 99 General And Miscellaneous//Mathematics, Power Reactors, Energy Transfer, & Computer Programs-- (1987-1989), Accidents, Peach Bottom-2 Reactor, Graphite Moderated Reactors, And Information Science, Water Cooled Reactors, Safety, Htgr Type Reactors, Computerized Models, Peach Bottom-1 Reactor, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
Blackouts, Enriched Uranium Reactors, Helium Cooled Reactors, 210100 -- Power Reactors, Boiling Water Cooled, Nonbreeding, Hydraulics, 990220 -- Computers, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Peach Bottom-3 Reactor, Mechanics, Reactor Accidents, Gas Cooled Reactors, C Codes, Corium, Light-Water Moderated, 22 General Studies Of Nuclear Reactors, Reactor Safety, Seals, Computer Codes, Computing, Containment, Thermal Reactors, Heat Transfer, Bwr Type Reactors, Reactors, 99 General And Miscellaneous//Mathematics, Power Reactors, Energy Transfer, & Computer Programs-- (1987-1989), Accidents, Peach Bottom-2 Reactor, Graphite Moderated Reactors, And Information Science, Water Cooled Reactors, Safety, Htgr Type Reactors, Computerized Models, Peach Bottom-1 Reactor, Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
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