Fuel Grading Study on a Low-Enriched Uranium Fuel Design for the High Flux Isotope Reactor

Ilas, Germina ; Primm, Trent

Oak Ridge National Laboratory

关键词: Uranium;    Hfir Reactor;    Neutron Flux;    Ornl;    Targets;   

DOI  :  10.2172/970909
RP-ID  :  ORNL/TM-2009/223
RP-ID  :  DE-AC05-00OR22725
RP-ID  :  970909

美国|英语

来源: UNT Digital Library

【 摘 要 】

An engineering design study that would enable the conversion of the High Flux Isotope Reactor (HFIR) from high-enriched uranium to low-enriched uranium fuel is ongoing at Oak Ridge National Laboratory. The computational models used to search for a low-enriched uranium (LEU) fuel design that would meet the requirements for the conversion study, and the recent results obtained with these models during FY 2009, are documented and discussed in this report. Estimates of relevant reactor performance parameters for the LEU fuel core are presented and compared with the corresponding data for the currently operating high-enriched uranium fuel core. These studies indicate that the LEU fuel design would maintain the current performance of the HFIR with respect to the neutron flux to the central target region, reflector, and beam tube locations.