Study of UO2 wafer fuel for very high-power research reactors
Description
The Reduced Enrichment Research and Test Reactor Program is aimed at reducing fuel enrichment to < 20% in those research and test reactors presently using highly enriched uranium fuel. UO2 caramel fuel is one of the most promising new types of reduced-enrichment fuel for use in research reactors with very high power density. Parametric studies have been carried out to determine the maximum specific power attainable without significant fission-gas release for UO2 wafers ranging from 0.75 to 1.50 mm in thickness. The results indicate that: (1) all the fuel designs considered in this study are predicted not to fail under full-power operation up to a burnup of 1.09 x 1021 fis/cm3; (2) for all fuel designs, failure is predicted at approximately the same fuel centerline temperature for a given burnup; (3) the thinner the wafer, the wider the margin for fuel specific power between normal operation and increased-power operation leading to fuel failure; (4) increasing the coolant pressure in the reactor core could improve fuel performance by maintaining the fuel at a higher power level without failure for a given burnup; and (5) for a given power level, fuel failure will occur earlier at a higher cladding surface temperature and/or under power-cycling conditions
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on development, fabrication and application of reduced enrichment fuels for research and test reactors
- Journal Page Range
- p. 319-344.
- Report number
- ANL/RERTR/TM--3
Conference
- Title
- International meeting on development, fabrication, and application of reduced-enrichment fuels for research and test reactors.
- Dates
- 13-14 Nov 1980.
- Place
- Argonne, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15010327
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM COMPOUNDS; BURNUP; FABRICATION; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; MATHEMATICAL MODELS; MODERATELY ENRICHED URANIUM; MOLYBDENUM COMPOUNDS; OSIRIS REACTOR; PERFORMANCE; PROLIFERATION; REACTOR CORES; RESEARCH AND TEST REACTORS; SILICON COMPOUNDS; SPECIFICATIONS; SWELLING; THERMAL CONDUCTIVITY; URANIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; DEFORMATION; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MATERIALS TESTING REACTORS; METALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT COMPOUNDS; URANIUM; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS