The use of U/sub 3/Si/sub 2/ dispersed in aluminum in plate-type fuel elements for research and test reactors
A high-density fuel based on U/sub 3/Si/sub 2/ dispersed in aluminum has been developed and tested for use in converting plate-type research and test reactors from the use of highly enriched uranium to the use of low-enriched uranium. Results of preirradiation testing and the irradiation and postirradiation examination of miniature fuel plates and full-sized fuel elements are summarized. Swelling of the U/sub 3/Si/sub 2/ fuel particles is a linear function of the fission density in the particle to well beyond the fission density achievable in low-enriched fuels. U/sub 3/Si/sub 2/ particle swelling rate is approximately the same as that of the commonly used UAl/sub x/ fuel particle. The presence of minor amounts of U/sub 3/Si or uranium solid solution in the fuel result in greater, but still acceptable, fuel swelling. Blister threshold temperatures are at least as high as those of currently used fuels. An exothermic reaction occurs near the aluminum melting temperature, but the measured energy releases were low enough not to substantially worsen the consequences of an accident. U/sub 3/Si/sub 2/-aluminum dispersion fuel with uranium densities up to at least 4.8 Mg/m/sup 3/ is a suitable LEU fuel for typical plate-type research and test reactors. 42 refs., 28 figs., 7 tabs.
- Research Organization:
- Argonne National Lab., IL (USA); Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5688807
- Report Number(s):
- ANL/RERTR/TM-11; ON: DE88003714
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fuel development activities of the US RERTR Program. [Reduced Enrichment Research and Test Reactor]
Irradiation behavior of intermetallic uranium compounds used as fuel for research and test reactors
Prospects of stable high-density dispersion fuels
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5532823
Irradiation behavior of intermetallic uranium compounds used as fuel for research and test reactors
Conference
·
Wed Dec 31 23:00:00 EST 1986
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6981548
Prospects of stable high-density dispersion fuels
Conference
·
Thu Oct 01 00:00:00 EDT 1987
·
OSTI ID:5292108
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
36 MATERIALS SCIENCE
360101 -- Metals & Alloys-- Preparation & Fabrication
360104 -- Metals & Alloys-- Physical Properties
ACTINIDE ALLOYS
ACTINIDE COMPOUNDS
ACTINIDES
ALLOYS
ALUMINIUM ALLOYS
BLISTERS
BURNUP
CORROSION RESISTANCE
CRYSTAL STRUCTURE
DIAGRAMS
DISPERSION NUCLEAR FUELS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FABRICATION
FUEL ELEMENTS
FUEL PLATES
FUELS
HEAT TREATMENTS
INTERMETALLIC COMPOUNDS
ISOTOPE ENRICHED MATERIALS
MATERIALS
MATERIALS TESTING
MATRIX MATERIALS
METALS
MICROSTRUCTURE
NUCLEAR FUELS
PHASE DIAGRAMS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
POROSITY
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SILICIDES
SILICON ALLOYS
SILICON COMPOUNDS
SLIGHTLY ENRICHED URANIUM
SOLID FUELS
SWELLING
TEST REACTORS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM
URANIUM ALLOYS
URANIUM COMPOUNDS
URANIUM SILICIDES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360101 -- Metals & Alloys-- Preparation & Fabrication
360104 -- Metals & Alloys-- Physical Properties
ACTINIDE ALLOYS
ACTINIDE COMPOUNDS
ACTINIDES
ALLOYS
ALUMINIUM ALLOYS
BLISTERS
BURNUP
CORROSION RESISTANCE
CRYSTAL STRUCTURE
DIAGRAMS
DISPERSION NUCLEAR FUELS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FABRICATION
FUEL ELEMENTS
FUEL PLATES
FUELS
HEAT TREATMENTS
INTERMETALLIC COMPOUNDS
ISOTOPE ENRICHED MATERIALS
MATERIALS
MATERIALS TESTING
MATRIX MATERIALS
METALS
MICROSTRUCTURE
NUCLEAR FUELS
PHASE DIAGRAMS
PHYSICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
POROSITY
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SILICIDES
SILICON ALLOYS
SILICON COMPOUNDS
SLIGHTLY ENRICHED URANIUM
SOLID FUELS
SWELLING
TEST REACTORS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM
URANIUM ALLOYS
URANIUM COMPOUNDS
URANIUM SILICIDES