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
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
BUILDING MATERIALS
BUILDINGS
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
ENERGY TRANSFER
FILM BOILING
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MATERIALS
MECHANICS
MELTDOWN
PHASE TRANSFORMATIONS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS