DESIGN STUDY FOR A LOW-ENRICHED URANIUM CORE FOR THE HIGH FLUX ISOTOPE REACTOR, ANNUAL REPORT FOR FY 2010

Cook, David Howard ; Freels, James D. ; Ilas, Germina ; Jolly, Brian C. ; Miller, James Henry ; Primm, R. Trent, III ; Renfro, David G. ; Sease, John D. ; Pinkston, Daniel

Oak Ridge National Laboratory

关键词: Hfir Leu Fuel Development Reactor Physics Annual Report 2010;    Alloys;    Uranium;    Implementation;    Hfir Reactor;   

DOI  :  10.2172/1004673
RP-ID  :  ORNL/TM-2011/6
RP-ID  :  DE-AC05-00OR22725
RP-ID  :  1004673

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来源: UNT Digital Library

【 摘 要 】

This report documents progress made during FY 2010 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 performance to users from the current level. Studies are reported of support to a thermal hydraulic test loop design, the implementation of finite element, thermal hydraulic analysis capability, and infrastructure tasks at HFIR to upgrade the facility for operation at 100 MW. A discussion of difficulties with preparing a fuel specification for the uranium-molybdenum alloy is provided. Continuing development in the definition of the fuel fabrication process is described.