Post-accident heat removal with advanced LMFBR fuels

Technical Report · Sat Mar 01 00:00:00 EDT 1975

OSTI ID:6278617

Gasser, R D; Catton, I; Kastenberg, W E

An analysis is performed to study the problems associated with retaining and cooling the debris subsequent to a postulated LMFBR core disassembly and meltdown accident, with emphasis placed on advanced reactor fuels such as the carbides and nitrides of uranium and plutonium. A heat transfer model for the fluidized particle bed is constructed, and a solution generated to obtain maximum bed depth at which incipent sodium boiling occurs. Experimental data for dryout in a fluidized particle bed with volumetric heating are analyzed and corrections made to adjust for sodium as a working fluid and for the effective density of the particulate. Finally, a convective heat transfer correlation for a molten layer is used to determine the layer thickness for which incipent sodium boiling occurs at the lower surface of a core catcher.

• Research Organization: California Univ., Los Angeles (USA). Dept. of Energy and Kinetics
• DOE Contract Number: AM03-76SF00034
• OSTI ID: 6278617
• Report Number(s): UCLA-340222and223-1; UCLA-ENG-7518
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
CORE CATCHERS
NATURAL CONVECTION
LMFBR TYPE REACTORS
MELTDOWN
HEAT TRANSFER
HYDRAULICS
AFTER-HEAT
CORIUM
REACTOR CORE DISRUPTION
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
CONVECTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
REMOVAL
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding