Disposition of Unirradiated Sodium Bonded EBR-II Driver Fuel Elements and HEU Scrap: Work Performed for FY 2007

Karen A Moore

关键词: S;    CASTING;    DOCUMENTATION;    ENRICHED URANIUM;    FABRICATION;    FUEL CANS;    FUEL ELEMENTS;    IDAHO;    MODIFICATIONS;    PROCESSING;    REACTORS;    REMOVAL;    SAFETY;    SCRAP;    SODIUM;    TRANSPORT Disposition;    HEU;    sodium-bonded fuel;   

DOI  :  10.2172/918170
RP-ID  :  INL/EXT-07-12513
PID  :  OSTI ID: 918170
Others  :  TRN: US0805372

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

Specific surplus high enriched uranium (HEU) materials at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) will be transferred to a designated off-site receiving facility. The DOE High Enriched Uranium Disposition Program Office (HDPO) will determine which materials, if any, will be prepared and transferred to an off-site facility for processing and eventual fabrication of fuel for nuclear reactors. These surplus HEU materials include approximately 7200 kg unirradiated sodium-bonded EBR-II driver fuel elements, and nearly 800 kg of HEU casting scrap from the process which formed various sodium-bonded fuels (including the EBR-II driver elements). Before the driver fuel can be packaged for shipment, the fuel elements will require removal of the sodium bond. The HEU scrap will also require repackaging in preparation for off-site transport. Preliminary work on this task was authorized by BWXT Y-12 on Nov 6, 2006 and performed in three areas: • Facility Modifications • Safety Documentation • Project Management