Production of spherical UO/sub 2/-UC/sub 2/ for nuclear fuel applications using thermochemical principles
Journal Article
·
· J. Am. Ceram. Soc.; (United States)
A process for the fabrication of uranium dioxide-uranium dicarbide microspheres for use as an advanced nuclear fuel is described. The uranium-carbon-oxygen phase diagram was used extensively in applying thermochemical principles to the combined process of uranium carbide synthesis and kernel sintering. A procedure was developed to convert urania plus carbon microspheres produced by a wet-chemical gelation process to a highly dense UO/sub 2/-UC/sub 2/ product. 22 refs.
- Research Organization:
- Oak Ridge Natl Lab, TN, USA
- OSTI ID:
- 6494809
- Journal Information:
- J. Am. Ceram. Soc.; (United States), Journal Name: J. Am. Ceram. Soc.; (United States) Journal Issue: 7 Vol. 65:7; ISSN JACTA
- 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
Production of spherical UO/sub 2/-UC/sub 2/ for nuclear fuel applications using thermochemical principles
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres
Technical Report
·
Sat Feb 28 23:00:00 EST 1981
·
OSTI ID:6613953
Production of spherical UO/sub 2/-UC/sub 2/ for nuclear fuel applications using thermochemical principles
Journal Article
·
Thu Jul 01 00:00:00 EDT 1982
· J. Am. Ceram. Soc.; (United States)
·
OSTI ID:5880100
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres
Journal Article
·
Sat Nov 05 00:00:00 EDT 2016
· Journal of Nuclear Materials
·
OSTI ID:1360046
Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
CHEMICAL PREPARATION
FABRICATION
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
REACTORS
SINTERING
SYNTHESIS
THERMOCHEMICAL PROCESSES
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
CHEMICAL PREPARATION
FABRICATION
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
REACTORS
SINTERING
SYNTHESIS
THERMOCHEMICAL PROCESSES
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES