Evolution of service to the power reactor community at the UFTR - beyond the bottom line
Description
The University of Florida Training Reactor (UFTR) is a 100-kW light-water-cooled, graphite-and-light-water-moderated modified argonaut-type reactor. Although currently fueled with highly enriched (93% 235U) fuel, analyses are nearly completed for conversion to low-enriched fuel. The core design consists of individual fuel boxes in each of which flow is constrained which is a relatively unique feature among existing nonpower reactors (NPRs), making measurement of hot channel factors and other core parameters a straightforward exercise for operator trainees. Since first licensed to operate at 10 kill in 1959, this NPR facility has had an active but evolving record of continuous service to the power reactor community. Because of its midsize power level, available flux levels limit utilization for radiation damage and other studies in which utilities have been served by other NPR facilities. As a result, UFTR service to the power reactor community has been concentrated in areas where the peak thermal flux (∼2 x 1012 n/cm2 ·s) at full power does not present a significant limitation
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 69
- Journal Page Range
- p. 170-171.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 14-18 Nov 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26026188
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ARGONAUT TYPE REACTORS; DESIGN; FUEL CHANNELS; HOT CHANNEL; NEUTRON FLUX; REACTOR CORES; REACTOR OPERATION; UFTR REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; OPERATION; RADIATION FLUX; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; THERMAL REACTORS; TRAINING REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-931160--.