Thermodynamic measurement and modeling of (UC/sub 1-x O/sub x)
Conference
·
· J. Am. Ceram. Soc.; (United States)
OSTI ID:6982393
Measurements were made of (CO) pressure over (UC/sub 1-x/O/sub x/) at 1823, 1773, 1673, 1573, and 1473 K for various values of x, in the presence of (UC/sub 1/ /sub 86/). The data were used to model (UC/sub 1-x/O/sub x/) as a solid solution of (UC) and (UO), where deltaG/sup xs/ is represented by an expansion in two terms, the first of which is temperature-dependent. The model allows for the accurate prediction of chemical activities and phase equilibria in regions also containing (UC/sub 1/ /sub 86/), (UO/sub 2-y/), (UC/sub 1/ /sub 86/)-(UO/sub 2/), and (UO/sub 2-y/)-(U).
- Research Organization:
- Oak Ridge National Lab., TN
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6982393
- Conference Information:
- Journal Name: J. Am. Ceram. Soc.; (United States) Journal Volume: 66:5
- Country of Publication:
- United States
- Language:
- English
Similar Records
Production of spherical UO/sub 2/-UC/sub 2/ for nuclear fuel applications using thermochemical principles
On the product phases and the reaction kinetics of carbothermic reduction of UO2+C at relatively low temperatures
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres
Journal Article
·
Thu Jul 01 00:00:00 EDT 1982
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:5880100
On the product phases and the reaction kinetics of carbothermic reduction of UO2+C at relatively low temperatures
Journal Article
·
Fri Nov 01 20:00:00 EDT 2024
· Journal of Nuclear Materials
·
OSTI ID:2481161
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres
Journal Article
·
Fri Nov 04 20:00:00 EDT 2016
· Journal of Nuclear Materials
·
OSTI ID:1360046
Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
ELEMENTS
ENERGY SOURCES
FUELS
HIGH TEMPERATURE
MATERIALS
MATHEMATICAL MODELS
NONMETALS
NUCLEAR FUELS
OXYGEN
PHYSICAL PROPERTIES
REACTOR MATERIALS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM CARBIDES
URANIUM COMPOUNDS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
ELEMENTS
ENERGY SOURCES
FUELS
HIGH TEMPERATURE
MATERIALS
MATHEMATICAL MODELS
NONMETALS
NUCLEAR FUELS
OXYGEN
PHYSICAL PROPERTIES
REACTOR MATERIALS
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM CARBIDES
URANIUM COMPOUNDS