Transient core-debris bed heat-removal experiments and analysis. [PWR; BWR]
An experimental investigation is reported of the thermal interaction between superheated core debris and water during postulated light-water reactor degraded core accidents. Data are presented for the heat transfer characteristics of packed beds of 3 mm spheres which are cooled by overlying pools of water. Results of transient bed temperature and steam flow rate measurements are presented for bed heights in the range 218 mm-433 mm and initial particle bed temperatures between 530K and 972K. Results display a two-part sequential quench process. Initial frontal cooling leaves pockets or channels of unquenched spheres. Data suggest that heat transfer process is limited by a mechanism of countercurrent two-phase flow. An analytical model which combines a bed energy equation with either a quasisteady version of the Lipinski debris bed model or a critical heat flux model reasonably well predicts the characteristic features of the bed quench process. Implications with respect to reactor safety are discussed.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA); Lehigh Univ., Bethlehem, PA (USA). Dept. of Chemical Engineering
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6733928
- Report Number(s):
- BNL-NUREG-31796; CONF-820802-47; ON: DE83000712
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
BWR TYPE REACTORS
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
HYDRODYNAMICS
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MECHANICS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
TEMPERATURE GRADIENTS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS