Pour stream breakup of molten IFR (Integral Fast Reactor) metal fuel in sodium
Conference
·
OSTI ID:5158815
Tests have been conducted in which the breakup behavior of kilogram quantities of molten uranium, uranium-zirconium alloy, and uranium-iron alloy pour streams in 600C sodium was studied. A sodium depth of less than 0.3 m was required for hydrodynamic breakup and freezing of 25-mm pour streams of uranium and uranium-zirconium alloy with up to 400C melt superheat. The breakup material was primarily in the form of filaments and sheets with a settled bed voidage on the order of 0.9. The uranium-iron alloy with 800C melt superheat exhibited similar behavior except a sodium depth somewhat greater than 0.3 m was required for breakup and freezing of the particles.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5158815
- Report Number(s):
- CONF-880506-9; ON: DE88010002
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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220600 -- Nuclear Reactor Technology-- Research
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ACTINIDE ALLOYS
ACTINIDES
ALKALI METALS
ALLOYS
BREEDER REACTORS
DATA
ELEMENTS
ENERGY SOURCES
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FREEZING
FUELS
HEAT TRANSFER
HYDRAULICS
IFR REACTOR
INFORMATION
IRON
LIQUID FUELS
LIQUID METAL COOLED REACTORS
LIQUID METAL FUELS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
MELTING
MELTING POINTS
METALS
NUCLEAR FUELS
NUMERICAL DATA
PARTICLE SIZE
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SIZE
SODIUM
THERMODYNAMIC PROPERTIES
TRANSITION ELEMENTS
TRANSITION TEMPERATURE
URANIUM
URANIUM ALLOYS
ZERO POWER REACTORS
ZIRCONIUM
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ALLOYS
ACTINIDES
ALKALI METALS
ALLOYS
BREEDER REACTORS
DATA
ELEMENTS
ENERGY SOURCES
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL DATA
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FREEZING
FUELS
HEAT TRANSFER
HYDRAULICS
IFR REACTOR
INFORMATION
IRON
LIQUID FUELS
LIQUID METAL COOLED REACTORS
LIQUID METAL FUELS
LMFBR TYPE REACTORS
MATERIALS
MECHANICS
MELTING
MELTING POINTS
METALS
NUCLEAR FUELS
NUMERICAL DATA
PARTICLE SIZE
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SIZE
SODIUM
THERMODYNAMIC PROPERTIES
TRANSITION ELEMENTS
TRANSITION TEMPERATURE
URANIUM
URANIUM ALLOYS
ZERO POWER REACTORS
ZIRCONIUM