Design Study for a Low-Enriched Uranium Core for the High Flux Isotope Reactor, Annual report for FY 2009

Chandler, David¹  Freels, James D¹  Ilas, Germina¹  Miller, James Henry¹  Primm, Trent¹  Sease, John D¹  Guida, Tracey²  Jolly, Brian C¹ 

[1] ORNL;University of Pittsburgh

关键词: ALLOYS;    BENCHMARKS;    COATINGS;    DESIGN;    ENRICHED URANIUM;    HFIR REACTOR;    PERFORMANCE;    SILICON;    SPECIFICATIONS;    THERMAL HYDRAULICS;    URANIUM;    URANIUM OXIDES HFIR LEU annual report FY2009 RERTR;   

DOI  :  10.2172/972310
RP-ID  :  ORNL/TM-2009/313
PID  :  OSTI ID: 972310
Others  :  Other: NN9002000
Others  :  MDGA518
Others  :  TRN: US1001499

美国|英语

来源: SciTech Connect

【 摘 要 】

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.