Investigation of the low enrichment conversion of the Texas A and M Nuclear Science Center Reactor

Technical Report · Fri Jan 01 00:00:00 EST 1988

DOI:https://doi.org/10.2172/5741582· OSTI ID:5741582

Reuscher, J A

The use of highly enriched uranium as a fuel research reactors is of concern due to the possibility of diversion for nuclear weapons applications. The Texas A M TRIGA reactor currently uses 70% enriched uranium in a FLIP (Fuel Life Improvement Program) fuel element manufactured by General Atomics. Thus fuel also contains 1.5 weight percent of erbium as a burnable poison to prolong useful core life. US university reactors that use highly enriched uranium will be required to covert to 20% or less enrichment to satisfy Nuclear Regulatory Commission requirements for the next core loading if the fuel is available. This investigation examined the feasibility of a material alternate to uranium-zirconium hydride for LEU conversion of a TRIGA reactor. This material is a beryllium oxide uranium dioxide based fuel. The theoretical aspects of core physics analyses were examined to assess the potential advantages of the alternative fuel. A basic model was developed for the existing core configuration since it is desired to use the present fuel element grid for the replacement core. The computing approach was calibrated to the present core and then applied to a core of BeO-UO{sub 2} fuel elements. Further calculations were performed for the General Atomics TRIGA low-enriched uranium zirconium hydride fuel.

• Research Organization: Texas A and M Univ., College Station, TX (USA). Nuclear Science Center
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: FG07-87ER75346
• OSTI ID: 5741582
• Report Number(s): DOE/ER/75346-T1; ON: DE91005588
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENRICHED URANIUM
CONVERSION
TRIGA-TEXAS REACTOR
BERYLLIUM OXIDES
CROSS SECTIONS
DIFFUSION
NUCLEAR DATA COLLECTIONS
PROGRESS REPORT
URANIUM OXIDES
ACTINIDE COMPOUNDS
ACTINIDES
ALKALINE EARTH METAL COMPOUNDS
BERYLLIUM COMPOUNDS
CHALCOGENIDES
DOCUMENT TYPES
ELEMENTS
ENRICHED URANIUM REACTORS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
IRRADIATION REACTORS
ISOTOPE ENRICHED MATERIALS
ISOTOPE PRODUCTION REACTORS
MATERIALS
METALS
OXIDES
OXYGEN COMPOUNDS
PULSED REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
THERMAL REACTORS
TRIGA TYPE REACTORS
URANIUM
URANIUM COMPOUNDS
WATER COOLED REAC
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors