Significant results of neutronics analysis for fuel conversion of the UFTR
Abstract
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.
- Authors:
-
- Univ. of Florida, Gainesville (United States)
- Publication Date:
- OSTI Identifier:
- 6670580
- Report Number(s):
- CONF-921102-
Journal ID: ISSN 0003-018X; CODEN: TANSAO
- Resource Type:
- Conference
- Journal Name:
- Transactions of the American Nuclear Society; (United States)
- Additional Journal Information:
- Journal Volume: 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; Journal ID: ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NUCLEAR FUELS; NUCLEAR FUEL CONVERSION; ARGONAUT TYPE REACTORS; FUEL PLATES; LICENSING; REACTOR PHYSICS; UFTR REACTOR; URANIUM SILICIDES; ACTINIDE COMPOUNDS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; PHYSICS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICIDES; SILICON COMPOUNDS; THERMAL REACTORS; TRAINING REACTORS; URANIUM COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors
Citation Formats
Vernetson, W G. Significant results of neutronics analysis for fuel conversion of the UFTR. United States: N. p., 1992.
Web.
Vernetson, W G. Significant results of neutronics analysis for fuel conversion of the UFTR. United States.
Vernetson, W G. 1992.
"Significant results of neutronics analysis for fuel conversion of the UFTR". United States.
@article{osti_6670580,
title = {Significant results of neutronics analysis for fuel conversion of the UFTR},
author = {Vernetson, W G},
abstractNote = {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.},
doi = {},
url = {https://www.osti.gov/biblio/6670580},
journal = {Transactions of the American Nuclear Society; (United States)},
issn = {0003-018X},
number = ,
volume = 66,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1992},
month = {Wed Jan 01 00:00:00 EST 1992}
}