Analytical formula for fuel particle to liquid sodium heat transfer
Analytical formula for fuel particle to liquid sodium heat transfer
In the analysis of unprotected loss-of-flow and overpower transients of liquid metal fast breeder reactors, the modeling of heat transfer from molten fuel, ejected into the coolant channel after cladding rupture, to liquid sodium is an important part of fuel-coolant interaction (FCI). Some of the ejected molten fuel fragments into small particles and gets dispersed in the coolant. In the PLUT02 code model and other modeling efforts of FCI it is assumed that the fuel particle to liquid sodium heat transfer is limited only by the thermal conduction resistance of the fuel because the thermal conductivity of liquid sodium is about 30 times higher than that of mixed oxide. The fuel particle (assumed to be a sphere) surface temperature, under this assumption, equals the coolant temperature. The purpose of the present analysis is to obtain the value of meter C/sub 1/ (for V/sub l/ = 1) by solving the linear transient heat conduction equation a constant parameter in the equation for evaluating the fuel-coolant heat transfer coefficient.
- University of North Texas United States
- University of North Texas United States
Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Mathematical Models, Safety 220900* -- Nuclear Reactor Technology-- Reactor Safety, Breeder Reactors, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Fuel-Coolant Interactions, Breeding, Heat Transfer, Reactors, Mechanics, Reactor Accidents, 210500 -- Power Reactors, Transient Overpower Accidents, Fbr Type Reactors, Energy Transfer, Fast Reactors, Lmfbr Type Reactors, Accidents, Epithermal Reactors, Loss Of Flow, Liquid Metal Cooled Reactors
Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Mathematical Models, Safety 220900* -- Nuclear Reactor Technology-- Reactor Safety, Breeder Reactors, Hydraulics, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Fuel-Coolant Interactions, Breeding, Heat Transfer, Reactors, Mechanics, Reactor Accidents, 210500 -- Power Reactors, Transient Overpower Accidents, Fbr Type Reactors, Energy Transfer, Fast Reactors, Lmfbr Type Reactors, Accidents, Epithermal Reactors, Loss Of Flow, Liquid Metal Cooled Reactors
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