Model for superheated debris-bed quench for severe-accident containment calculations. [PWR; BWR]. CONF-831047--85
Core meltdown accidents are being analyzed to develop an understanding of the risk associated with such postulated accidents and to evaluate the impact of possible mitigating engineering safety equipment. An integral feature of these analyses is the determination of containment building pressurization as a result of loadings imposed by the energy stored in the molten core debris. A major source of containment pressurization would result from the ex-vessel thermal interaction between molten core debris and water available beneath the reactor vessel. It has been suggested that the thermal interaction would occur in two stages: (1) the melt fall period during which the melt mixes with water, breaks up and transfers energy to the coolant, and (2) the debris bed or molten pool quench period during which the core debris rests on the concrete beneath the vessel and is cooled by an overlying pool of water. This paper is directed towards development of models to predict the thermal-hydraulic characteristics of superheated beds of solidified core debris which are cooled by water supplied by an overlying pool of water.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5845836
- Report Number(s):
- BNL-NUREG-33574; ON: DE83017586
- Country of Publication:
- United States
- Language:
- English
Similar Records
Quench cooling of superheated debris beds in containment during LWR core meltdown accidents
Measurements and analysis of steam generators rate from quenching of superheated debris beds. [PWR; BWR]
Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS