Summary Report on the HFED (High-Uranium-Loaded Fuel Element Development) Miniplate Irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program
Summary Report on the HFED (High-Uranium-Loaded Fuel Element Development) Miniplate Irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program

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Published: 1989

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An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was performed for the US Department of Energy Reduced Enrichment Research and Test Reactor Program. The experiment included the irradiation of 244 miniature fuel plates (miniplates) in a core position in the Oak Ridge Research Reactor. The miniplates were aluminum-based, dispersion-type plates 114.3 mm long by 50.8 mm wide with overall plate thicknesses of 1.27 or 1.52 mm. Fuel core dimensions varied according to the overall plate thicknesses with a minimum clad thickness of 0.20 mm. Tested fuels included UAl(subscript x), UAl2, U3O, U3SiAl, U3Si, U3Si/sub 1.5/, U3Si2, U3SiCu, USi, U6Fe, and U6Mn/sub 1.3/ materials. Although most miniplates were made with low-enriched uranium (19.9%), some with medium-enriched uranium (40 to 45%), a few with high-enriched uranium (93%), and a few with depleted uranium (0.2 to 0.4%) were tested for comparison. These fuel materials were irradiated to burnups ranging from (approximately)27 to 98 at. % 235U depletion. Operation of the experiment, measurement of miniplate thickness as the irradiation progressed, ultimate shipment of the irradiated miniplates to various hot cells, and preliminary results are reported here. 18 refs., 12 figs., 7 tabs.

RERTR Program Progress in Qualifying Reduced-enrichment Fuels
RERTR Program Progress in Qualifying Reduced-enrichment Fuels

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Published: 1982

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In order to provide the technical means for reducing the enrichment of uranium used to fuel research and test reactors, the US Reduced Enrichment Research and Test Reactor (RERTR) Program has been engaged in the development and testing of higher-uranium-density fuels than had been used previously. The main characteristics to be considered in evaluating the performance of a fuel are its swelling, its blister-threshold temperature, and its metallurgical appearance. Data for the qualification of the reduced-enrichment fuels being developed by the RERTR Program are obtained from examination of minature fuel plates (miniplates) which successfully pass the irradiation screening tests and from examinations of full-sized fuel elements. This paper will summarize the miniplate data and will give the status of full-sized element irradiations. Finally, the current status of qualification of the various fuel types will be discussed and some projections of the future will be given.

Irradiation Testing of Miniature Fuel Plates for the RERTR Program. [Reduced Enrichment Research and Test Reactors].
Irradiation Testing of Miniature Fuel Plates for the RERTR Program. [Reduced Enrichment Research and Test Reactors].

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Published: 1981

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An irradiation test facility, which provides a test bed for irradiating a variety of miniature fuel plates (miniplates) for the Reduced Enrichment Research and Test Reactors (RERTR) program, has been placed into operation. These tests screen various candidate fuel materials on their suitability for replacing the highly enriched uranium fuel materials currently used by the world's test and research reactors with a lower enrichment fuel material, without significantly degrading reactor operating characteristics and power levels. The use of low uranium enrichment of about 20% 235U in place of highly enriched fuel for these reactors would reduce the potential for 235U diversion. The irradiation test facility, designated as HFED, is operating in core position E-7 in the Oak Ridge Research Reactor (ORR), a 30-MW water-moderated reactor. The miniplates will achieve burnups of up to approx. 2.2 x 1027 fissions/m3 of fuel.

Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position
Detailed Fission Power 2D-Mapping of AFIP-2 Experiment in ATR CFT Position

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Published: 2008

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The NNSA (National Nuclear Security Administration) RERTR (Reduced Enrichment for Research and Test Reactors) program assigned INL (Idaho National Laboratory) the responsibility of developing and demonstrating high uranium density research reactor fuel forms to enable the use of low enriched uranium (LEU) in the research reactors around the world. A series of full-size fuel plate irradiation tests are proposed for the ATR (Advanced Test Reactor). Labeled the AFIP (ATR Full-size-plates In center flux trap Position) experiments, these tests will be conducted in the ATR center flux trap. The AFIP-2 experiment will contain two full size fuel plates fabricated at the Oak Ridge National Laboratory-Y-12 (ORNL). The nominal fuel zone is rectangular in shape having a designed length of 21.5-in (54.6l-cm), width of 1.6-in (4.064-cm), and uniform thickness of 0.014-in (0.03556-cm). This gives a nominal fuel zone volume of 0.482 in3 (7.89 cm3) in each fuel plate. The test holder accommodates two independent test trains. Each test train is designed to hold 2 plates, for a total of 4 plates per test holder. AFIP-2 test plates will be irradiated at a peak surface heat flux of about 350 W/cm2 and discharged at a peak U-235 burn-up of about 70 at.%. Based on limited irradiation testing of the monolithic (U10Mo) fuel form, it is desirable to keep the peak fuel temperature below 250°C; to achieve this, it will be necessary to keep plate heat fluxes below 500 W/cm2. Due to the heavy U-235 loading and width of 1.6-in (4.064 cm), the neutron self-shielding will increase the local-to-average-ratio fission power near the sides of the fuel plates. To assure the AFIP-2 experiment will comply with the ATR safety requirements, a very detailed 2 dimensional (2D) Y-Z fission power profile was evaluated to best predict the fuel plate temperature distribution. The ability to accurately predict fuel plate power and burnup are essential in the AFIP-2 fuel test train design and the irradiated fuel performance evaluation. We obtained the required power and heat generation rates within test train for the thermal analyses. A detailed MCNP Y-Z mini-plate fuel model was developed. The Y-Z model divides each fuel mini-plate into 30 equal intervals in Y and Z directions. The MCNP-calculated results and the detailed Y-Z fission power mapping were used to help design the AFIP-2 fuel test assembly to ensure that the capsule thermal-hydraulic limits will not exceed the ATR safety limit.

Irradiation Performance of Reduced-enrichment Fuels Tested Under the US RERTR Program
Irradiation Performance of Reduced-enrichment Fuels Tested Under the US RERTR Program

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Published: 1985

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Considerable progress in the irradiation testing of high-density, reduced-enrichment fuels has been made during the past year. Miniplates containing UA1, U3Si2, U3Si/sub 1.5/, U3Si, U3SiCu, and, U6Fe have been irradiated. Postirradiation examinations have revealed that breakway swelling has occurred in 6.4-Mg U/m3 U3Si plates at approx. 2.8 x 1027 fissions/m3. U3Si2 plates are continuing to show satisfactory performance. The testing of full-sized fuel elements in the ORR and the SILOE reactor have continued with good results. Postirradiation examinations are confirming the satisfactory performance of these elements.