D7 debris-bed experiment. [LMFBR]
D7 debris-bed experiment. [LMFBR]
The D7 experiment investigated heat removal from a shallow, stratified bed of UO/sub 2/ particulate in sodium. The particle diameters ranged from 0.1 to 1.0 mm, with the largest particles at the bottom. The bed thickness was 74 mm and the average porosity was 41%. The incipient dryout power varied from 0.43 W/g to 0.25 W/g as the sodium subcooling (saturation temperature minus overlying pool temperature) was reduced from 390/sup 0/C to 170/sup 0/C. These powers were only slighlty above the incipient boiling powers. Such low dryout powers are believed due to the interaction of capillary force with bed stratification. With a subccoling of 130/sup 0/C several sudden decreases in the saturation temperature occurred. These are believed due to channel formation, which causes a reduction in the capillary pressure in the bed.
- Sandia National Laboratories United States
- University of North Texas United States
570, 791, Temperature Gradients, Hydraulics, Test Facilities, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Breeding, Mechanics, Actinide Compounds, Reactor Accidents, Alkali Metals, Containers, Fbr Type Reactors, After-Heat Removal, Lmfbr Type Reactors, Stresses, Corium, 22 General Studies Of Nuclear Reactors, Reactor Safety, After-Heat, Breeder Reactors, Sodium, Oxides, Heat Transfer, Reactors, Elements, Uranium Compounds, 210500 -- Power Reactors, Uranium Dioxide, Thermal Stresses, Reactor Vessels, Energy Transfer, Dryout, Fast Reactors, Metals, Accidents, Epithermal Reactors, Meltdown, Uranium Oxides 220900* -- Nuclear Reactor Technology-- Reactor Safety, Safety, Oxygen Compounds, Reactor Core Disruption, Removal, Liquid Metal Cooled Reactors, Chalcogenides
570, 791, Temperature Gradients, Hydraulics, Test Facilities, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Breeding, Mechanics, Actinide Compounds, Reactor Accidents, Alkali Metals, Containers, Fbr Type Reactors, After-Heat Removal, Lmfbr Type Reactors, Stresses, Corium, 22 General Studies Of Nuclear Reactors, Reactor Safety, After-Heat, Breeder Reactors, Sodium, Oxides, Heat Transfer, Reactors, Elements, Uranium Compounds, 210500 -- Power Reactors, Uranium Dioxide, Thermal Stresses, Reactor Vessels, Energy Transfer, Dryout, Fast Reactors, Metals, Accidents, Epithermal Reactors, Meltdown, Uranium Oxides 220900* -- Nuclear Reactor Technology-- Reactor Safety, Safety, Oxygen Compounds, Reactor Core Disruption, Removal, Liquid Metal Cooled Reactors, Chalcogenides
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