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U.S. Department of Energy
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Criticality Safety Studies of a Proposed Uranium-Zirconium Alloy Fuel Fabrication Facility

Conference ·
OSTI ID:5432075
 [1];  [2];  [1];  [2]
  1. Univ. of Tennessee, Knoxville, TN (United States)
  2. Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States)
The purpose of this project is to provide criticality limits and guidance for the initial planning phase of a new facility for the production of a new metal alloy fuel material for the Hanford N Reactor. The proposed fuel material composition is a uranium- zirconium alloy consisting of approximately 90.7 weight percent zirconium and 9.3 weight percent uranium. While the anticipated enrichments range from 55 to 70 weight percent 235U, this analysis considers only 100 weight percent 235U for simplicity and conservatism. The fuel material would be produced in the form of a solid, as-cast double billet using an arc melter process. Two finished billets result from one as-cast double billet. The production process poses several criticality safety concerns that require evaluation. The concerns include non-homogeneous alloy formation in the arc melter, as-cast billet storage, and finished billet storage. All analyses were performed using the KENO V.a module of the SCALE computer code system with the 27 group, ENDF-IV based cross section library.
Research Organization:
Oak Ridge Y-12 Plant (Y-12), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-84OS21400
OSTI ID:
5432075
Report Number(s):
Y/DD--454; CONF-900608--55-Vugraphs; ON: DE91017849
Country of Publication:
United States
Language:
English