Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual report for FY 2009
Creators
- 1. Oak Ridge National Laboratory, TN (United States)
- 2. University of Pittsburgh, PA (United States)
Description
This report documents progress made during FY 2009 in studies of converting the High Flux Isotope Reactor (HFIR) from high enriched uranium (HEU) fuel to low enriched uranium (LEU) fuel. Conversion from HEU to LEU will require a change in fuel form from uranium oxide to a uranium-molybdenum alloy. With axial and radial grading of the fuel foil and an increase in reactor power to 100 MW, calculations indicate that the HFIR can be operated with LEU fuel with no degradation in reactor performance from the current level. Results of selected benchmark studies imply that calculations of LEU performance are accurate. Studies are reported of the application of a silicon coating to surrogates for spheres of uranium-molybdenum alloy. A discussion of difficulties with preparing a fuel specification for the uranium-molybdenum alloy is provided. A description of the progress in developing a finite element thermal hydraulics model of the LEU core is provided.
Availability note (English)
Available from http://info.ornl.gov/sites/publications/files/Pub22559.pdf; PURL: https://www.osti.gov/servlets/purl/972310-9yEL2P/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 64 p.
- Report number
- ORNL/TM--2009/313
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 41043233
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALLOYS; BENCHMARKS; COATINGS; DESIGN; ENRICHED URANIUM; HFIR REACTOR; PERFORMANCE; SILICON; SPECIFICATIONS; THERMAL HYDRAULICS; URANIUM; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; ELEMENTS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MECHANICS; METALS; OXIDES; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEMIMETALS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- NN9002000; MDGA518; AC05-00OR22725
- Notes
- doi 10.2172/972310
- Funding organization
- NNSA USDOE - National Nuclear Security Administration (United States)