Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum. [Reduced Enrichment for Research and Test Reactor]
Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400/sup 0/C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of the plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (1) the reaction of the uranium silicide with aluminum to form U(AlSi)/sub 3/ and (2) the release of hydrogen and subsequent creep and pillowing of the fuel plate. 9 references, 4 figures, 6 tables.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6286269
- Report Number(s):
- CONF-8410173-4; ON: DE85004037
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum
Study of diffusion bond development in 6061 aluminum and its relationship to future high density fuels fabrication.
Postirradiation analysis of experimental uranium-silicide dispersion fuel plates
Journal Article
·
Sat Nov 30 23:00:00 EST 1985
· Nucl. Technol.; (United States)
·
OSTI ID:5967359
Study of diffusion bond development in 6061 aluminum and its relationship to future high density fuels fabrication.
Conference
·
Tue Oct 07 00:00:00 EDT 1997
·
OSTI ID:750439
Postirradiation analysis of experimental uranium-silicide dispersion fuel plates
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5451159
Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ALUMINIUM
CHEMICAL REACTIONS
COMPATIBILITY
DATA
DISPERSION NUCLEAR FUELS
ELEMENTS
ENERGY SOURCES
EXPERIMENTAL DATA
FUEL ELEMENTS
FUEL PLATES
FUELS
GAS YIELDS
INFORMATION
MATERIALS
MATRIX MATERIALS
METALS
NUCLEAR FUELS
NUMERICAL DATA
REACTOR COMPONENTS
REACTOR MATERIALS
SILICIDES
SILICON COMPOUNDS
SOLID FUELS
SWELLING
URANIUM COMPOUNDS
URANIUM SILICIDES
YIELDS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ALUMINIUM
CHEMICAL REACTIONS
COMPATIBILITY
DATA
DISPERSION NUCLEAR FUELS
ELEMENTS
ENERGY SOURCES
EXPERIMENTAL DATA
FUEL ELEMENTS
FUEL PLATES
FUELS
GAS YIELDS
INFORMATION
MATERIALS
MATRIX MATERIALS
METALS
NUCLEAR FUELS
NUMERICAL DATA
REACTOR COMPONENTS
REACTOR MATERIALS
SILICIDES
SILICON COMPOUNDS
SOLID FUELS
SWELLING
URANIUM COMPOUNDS
URANIUM SILICIDES
YIELDS