Thermochemistry of the U-O and Zr-O systems
Journal Article
·
· Journal of the American Ceramic Society; (United States)
- Univ. of California, Berkeley (United States)
The thermodynamic constraint relating the standard free energy of formation of an oxide (MO[sub C]) to its oxygen potentials has been used to develop the full spectrum of oxygen potentials of the U-O and Zr-O systems at high temperatures. Henry's law is applied to the metal region in the U-O system. Oxygen dissolution in liquid Zr has been shown to deviate only slightly from Henry's law, despite the high solubility. Minor modifications of the previously reported oxygen pressures in the two-phase regions of both of the U-O and Zr-O systems result from the requirement of satisfying the integral constraint. Oxygen pressures in the oxygen-containing metal regions where no data are available have also been estimated. The ensemble of the results is displayed in the form of oxygen isobars superimposed on the phase diagrams of the U-O and Zr-O systems. The oxygen pressure-temperature-composition relation of tetragonal ([beta]) ZrO[sub 2[plus minus]x] has also been established.
- DOE Contract Number:
- AC03-76SF00098
- OSTI ID:
- 6410570
- Journal Information:
- Journal of the American Ceramic Society; (United States), Journal Name: Journal of the American Ceramic Society; (United States) Vol. 76:5; ISSN 0002-7820; ISSN JACTAW
- Country of Publication:
- United States
- Language:
- English
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·
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Conference
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Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:7087601
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BUILDING MATERIALS
BUILDINGS
CHALCOGENIDES
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
DISSOLUTION
ELEMENTS
ENERGY
ENERGY SOURCES
FLUIDS
FREE ENERGY
FREE ENTHALPY
FUEL-CLADDING INTERACTIONS
FUELS
LIQUEFACTION
LIQUID METALS
LIQUIDS
MATERIALS
METALS
NONMETALS
NUCLEAR FUELS
OXIDES
OXYGEN
OXYGEN COMPOUNDS
OXYGEN POTENTIAL
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTOR SAFETY
SAFETY
SOLUBILITY
THERMOCHEMICAL PROCESSES
THERMODYNAMIC PROPERTIES
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BUILDING MATERIALS
BUILDINGS
CHALCOGENIDES
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CORIUM
DISSOLUTION
ELEMENTS
ENERGY
ENERGY SOURCES
FLUIDS
FREE ENERGY
FREE ENTHALPY
FUEL-CLADDING INTERACTIONS
FUELS
LIQUEFACTION
LIQUID METALS
LIQUIDS
MATERIALS
METALS
NONMETALS
NUCLEAR FUELS
OXIDES
OXYGEN
OXYGEN COMPOUNDS
OXYGEN POTENTIAL
PHYSICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTOR SAFETY
SAFETY
SOLUBILITY
THERMOCHEMICAL PROCESSES
THERMODYNAMIC PROPERTIES
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES