Gas bubbling-enhanced film boiling of Freon-11 on liquid metal pools. [PWR; BWR]
In the analysis of severe core damage accidents in LWRs, a major driving force which must be considered in evaluating containment loading and fission product transport is the ex-vessel interaction between molten core debris and structural concrete. Two computer codes have been developed for this purpose, the CORCON-MOD2 model of ex-vessel, core concrete interactions and the VANESA model for aerosol generation and fission product release as a result of molten core-concrete interactions. Under a wide spectrum of reactor designs and accident sequences, it is possible for water to come into contact with the molten core debris and form a coolant pool overlying the core debris which is attacking the concrete. As the concrete decomposes, noncondensable gases are released, which bubble through the melt and across the boiling interface, affecting the liquid-liquid boiling process. Currently, the CORCON code includes the classical Berenson model for film boiling over a horizontal flat plate for this phenomenon. The objectives of this activity are to investigate the influence of transverse noncondensable gas flux on the magnitude of the stable liquid-liquid film boiling heat flux and develop a gas flux-enhanced, liquid-liquid film boiling model for incorporation into the CORCON-MOD2 computer code to replace or modify the Berenson model.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5869187
- Report Number(s):
- BNL-NUREG-36035; CONF-850610-19; ON: TI85007924
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society, Boston, MA, USA, 9 Jun 1985
- Country of Publication:
- United States
- Language:
- English
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BWR TYPE REACTORS
CONTAINMENT BUILDINGS
MELTDOWN
THERMAL STRESSES
FILM BOILING
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
CONCRETES
CORIUM
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ACCIDENTS
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WATER MODERATED REACTORS
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