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. (ANL), Argonne, IL (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5688807
- Report Number(s):
- ANL/RERTR/TM-11; ON: DE88003714; TRN: 88-002731
- Resource Relation:
- Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALUMINIUM ALLOYS
POROSITY
SWELLING
DISPERSION NUCLEAR FUELS
MICROSTRUCTURE
PHYSICAL RADIATION EFFECTS
FUEL PLATES
SILICON ALLOYS
URANIUM ALLOYS
BLISTERS
BURNUP
CORROSION RESISTANCE
FABRICATION
HEAT TREATMENTS
INTERMETALLIC COMPOUNDS
MATERIALS TESTING
MATRIX MATERIALS
PHASE DIAGRAMS
SLIGHTLY ENRICHED URANIUM
TEST REACTORS
THERMAL CONDUCTIVITY
URANIUM SILICIDES
ACTINIDE ALLOYS
ACTINIDE COMPOUNDS
ACTINIDES
ALLOYS
CRYSTAL STRUCTURE
DIAGRAMS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FUEL ELEMENTS
FUELS
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NUCLEAR FUELS
PHYSICAL PROPERTIES
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SILICIDES
SILICON COMPOUNDS
SOLID FUELS
TESTING
THERMODYNAMIC PROPERTIES
URANIUM
URANIUM COMPOUNDS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
360101 - Metals & Alloys- Preparation & Fabrication
360104 - Metals & Alloys- Physical Properties
050700 - Nuclear Fuels- Fuels Production & Properties