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Title: Significant results of neutronics analysis for fuel conversion of the UFTR

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6670580
 [1]
  1. Univ. of Florida, Gainesville (United States)

The University of Florida Training Reactor (UFTR) is a 100-kW light-water-cooled, graphite and light-water-moderated Argonaut-type reactor that utilizes high-enriched (93%) materials test reactor-type (uranium-aluminum alloy) fuel plates in a two-slab core configuration consisting of 11-plate fuel bundles loaded into six fuel boxes. The purpose of this work was to perform the neutronics analysis necessary to support a licensing submittal to the US Nuclear Regulatory Commission (NRC) for conversion of the UFTR from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel as required by 1986 revisions to the Code of Federal Regulations (10CFR50.64). After elimination of pin-type SPERT fuel as an option, the fuel selected for the conversion analysis was the uranium silicide-aluminum dispersion standard plate-type fuel, which has been well evaluated for use in nonpower reactor fuel conversions.

OSTI ID:
6670580
Report Number(s):
CONF-921102-; CODEN: TANSAO
Journal Information:
Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
Country of Publication:
United States
Language:
English