The Whole-Core LEU U3Si2-Al Fuel Demonstration in the 30-MW Oak Ridge Research Reactor
Description
The ORR Whole-Core LEU Fuel Demonstration, conducted as part of the US Reduced Enrichment Research and Test Reactor Program, has been successfully completed. Using commercially-fabricated U3Si2-Al 20%-enriched fuel elements (4.8 g U/cc) and fuel followers (3.5 g U/cc), the 30-MW Oak Ridge Research Reactor was safely converted from an all-HEU core, through a series of HEU/LEU mixed transition cores, to an all-LEU core. There were no fuel element failures and average discharge burnups were measured to be as high as 50% for the standard elements and 75% for the fuel followers. Experimental results for burnup-dependent critical configurations, cycle-averaged fuel element powers, and fuel-element-averaged 235U burnups, validated predictions based on three-dimensional depletion calculations. Calculated values for plutonium production and isotopic mass ratios as functions of 235U burnup support the corresponding measured quantities. In general, calculations for 60Co and 198Au reaction rate distributions, differential and integral control rod worths, prompt neutron decay constants, and isothermal temperature coefficients were found to agree with corresponding measured values. Experimentally determined critical configurations for fresh HEU and LEU cores radially reflected with water and with beryllium are well-predicted by both Monte Carlo and diffusion calculations. 44 refs., 57 figs., 45 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92000351; NTIS; INIS; US Govt. Printing Office Dep.Files
23011835.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 311 p.
- Report number
- ANL/RERTR/TM--14
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23011835
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BERYLLIUM; BURNUP; CALCULATION METHODS; COBALT 60; CONTROL ROD WORTHS; CRITICALITY; D CODES; DATA PROCESSING; DEMONSTRATION PROGRAMS; DIFFUSION; E CODES; FUEL ELEMENTS; GAMMA FUEL SCANNING; GOLD 198; HELIUM 3; HIGHLY ENRICHED URANIUM; LITHIUM 6; MONTE CARLO METHOD; NEUTRON REFLECTORS; ORR REACTOR; PLUTONIUM; R CODES; REACTIVITY; REACTOR CORES; REACTOR KINETICS; REACTOR SAFETY; SLIGHTLY ENRICHED URANIUM; T CODES; TEST FACILITIES; URANIUM SILICATES; URANIUM 235; V CODES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ACTINIDES; ALKALINE EARTH METALS; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COBALT ISOTOPES; COMPUTER CODES; DAYS LIVING RADIOISOTOPES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; FUEL SCANNING; GOLD ISOTOPES; HEAVY NUCLEI; HELIUM ISOTOPES; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPE ENRICHED MATERIALS; ISOTOPES; KINETICS; LIGHT NUCLEI; LITHIUM ISOTOPES; MATERIALS; METALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; ODD-ODD NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; REACTOR COMPONENTS; REACTORS; SAFETY; SILICATES; SILICON COMPOUNDS; SPONTANEOUS FISSION RADIOISOTO; STABLE ISOTOPES; TANK TYPE REACTORS; TRANSURANIUM ELEMENTS; URANIUM; URANIUM COMPOUNDS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Funding organization
- USDOE, Washington, DC (United States).