Safety evaluation report related to the evaluation of low-enriched uranium silicide-aluminum dispersion fuel for use in non-power reactors
Low-enriched uranium silicide-aluminum dispersion plate-type fuels have been extensively researched and developed under the international program, Reduced Enrichment in Research and Test Reactors. The international effort was led by Argonne National Laboratory (ANL) in the United States. This evaluation is based primarily on reports issued by ANL that discuss and summarize the developmental tests and experiments, including postirradiation examinations, of both miniature and full-sized plates of prototypical fuel compositions. This evaluation concludes that plate-type fuels suitable and acceptable for use in research and test reactors can be fabricated with U/sub 3/Si/sub 2/-Al dispersion compacts with uranium densities up to 4.8 g/cm/sup 3/. 4 refs., 1 fig.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (USA). Office of Nuclear Reactor Regulation
- OSTI ID:
- 6830338
- Report Number(s):
- NUREG-1313; ON: TI88015541; TRN: 88-032023
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
DISPERSION NUCLEAR FUELS
REACTOR SAFETY
RESEARCH AND TEST REACTORS
ALUMINIUM
EVALUATION
FUEL ELEMENTS
INTERNATIONAL COOPERATION
MECHANICAL PROPERTIES
POST-IRRADIATION EXAMINATION
RESEARCH PROGRAMS
THERMAL CONDUCTIVITY
URANIUM SILICIDES
ACTINIDE COMPOUNDS
COOPERATION
ELEMENTS
ENERGY SOURCES
FUELS
MATERIALS
METALS
NUCLEAR FUELS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SAFETY
SILICIDES
SILICON COMPOUNDS
SOLID FUELS
THERMODYNAMIC PROPERTIES
URANIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220300 - Nuclear Reactor Technology- Fuel Elements