Liquid uranium reaction with coated graphite crucibles
Technical Report
·
OSTI ID:6607285
Carbon contamination in uranium from yttria-coated graphite crucibles containing uncoated defects has been measured at typical foundry melting conditions as a function of defect area. The reaction of liquid uranium with graphite at crucible coating defects is proportional to the defect surface area and is approx.270 times greater than the reaction at a coated region of equivalent area. Uranium carbon contamination is much more sensitive to coating defects than to furnace pressure, coating-graphite reaction, or binder outgassing. Although the typical contribution of coating defects is small, perturbations in production crucible loading or coating procedures could increase the defect area to produce uranium alloy castings with high carbon content.
- Research Organization:
- Oak Ridge Y-12 Plant, TN (USA)
- DOE Contract Number:
- AC05-84OS21400
- OSTI ID:
- 6607285
- Report Number(s):
- Y-2379; ON: DE87009251
- 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
36 MATERIALS SCIENCE
360101* -- Metals & Alloys-- Preparation & Fabrication
ACTINIDE ALLOYS
ALLOYS
CARBON
CHEMICAL REACTIONS
COATINGS
CRUCIBLES
DEFECTS
ELEMENTAL MINERALS
ELEMENTS
FLUIDS
GRAPHITE
IMPURITIES
LIQUID METALS
LIQUIDS
MELTING
METALS
MINERALS
NONMETALS
PHASE TRANSFORMATIONS
URANIUM ALLOYS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
360101* -- Metals & Alloys-- Preparation & Fabrication
ACTINIDE ALLOYS
ALLOYS
CARBON
CHEMICAL REACTIONS
COATINGS
CRUCIBLES
DEFECTS
ELEMENTAL MINERALS
ELEMENTS
FLUIDS
GRAPHITE
IMPURITIES
LIQUID METALS
LIQUIDS
MELTING
METALS
MINERALS
NONMETALS
PHASE TRANSFORMATIONS
URANIUM ALLOYS