Downward heat transfer from heat-generating boiling pools pertaining to PAHR and transition phase. [LMFBR]
Conference
·
OSTI ID:5701329
The phenomenon of heat transfer from volume heated boiling pools in the downward direction is of considerable interest in nuclear reactor safety analysis. For example, in the post-accident heat removal studies of LMFBRs the downward heat transfer to a boiling steel layer in molten pool penetration of the MgO substrate is of interest. The bubbles rising from the boiling of stainless steel film, lying at the bottom of the heat generating pool consistaing of MgO and UO/sub 2/ eutectic solution, cause the upward motion of bulk fluid. This buoyancy effect of two-phase bulk fluid generates a negative pressure gradient along the base, resulting in motion of single-phase fluid in a boundary layer over the stainless steel liquid film. The heat transfer from concrete substrate during molten pool penetration or during sodium-concrete reaction also takes place owing to convection that is driven by gas and water vapor bubbles released from the concrete substrate due to its heatup. The proposed model assumes that owing to the density difference caused by volume boiling or bulk two-phase fluid between the bulk fluid and that near the base of the pool, the lighter two-phase bulk fluid causes upward movement of the fluid and thereby generates a negative pressure gradient along the base of the pool. This in turn causes motion of returning single-phase fluid along the base of the pool in laminar/turbulent boundary layers.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5701329
- Report Number(s):
- CONF-831047-68; ON: DE83015368
- Country of Publication:
- United States
- Language:
- English
Similar Records
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· J. Heat Transfer; (United States)
·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AFTER-HEAT
AFTER-HEAT REMOVAL
ALKALI METALS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CHROMIUM ALLOYS
CONCRETES
CORIUM
CORROSION RESISTANT ALLOYS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
MECHANICS
MELTDOWN
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
SODIUM
STAINLESS STEELS
STEELS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AFTER-HEAT
AFTER-HEAT REMOVAL
ALKALI METALS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
BREEDER REACTORS
BUILDING MATERIALS
CHALCOGENIDES
CHROMIUM ALLOYS
CONCRETES
CORIUM
CORROSION RESISTANT ALLOYS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
MECHANICS
MELTDOWN
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
SODIUM
STAINLESS STEELS
STEELS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES