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RERTR-7 Irradiation Summary Report

Description: The Reduced Enrichment for Research and Test Reactor (RERTR) experiment RERTR-7A, was designed to test several modified fuel designs to target fission densities representative of a peak low enriched uranium (LEU) burnup in excess of 90% U-235 at peak experiment power sufficient to generate a peak surface heat flux of approximately 300 W/cm2. The RERTR-7B experiment was designed as a high power test of 'second generation' dispersion fuels at peak experiment power sufficient to generate a surface… more
Date: December 1, 2011
Creator: Perez, D. M.; Lillo, M. A.; Chang, G. S.; Roth, G. A.; Woolstenhulme, N. E. & Wachs, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety analysis of the Los Alamos critical experiments facility: burst operation of Skua

Description: A detailed consideration of the Skua burst assembly is presented, thereby supplementing the facility safety analysis report covering the operation of other critical assemblies at Los Alamos. As with these assemblies the small fission-product inventory, ambient pressure, and moderate temperatures in Skua are amenable to straightforward measures to ensure the protection of the public.
Date: May 1, 1979
Creator: Orndoff, J. D.; Paxton, H. C. & Wimett, T. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress of the RERTR program in 2001.

Description: This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of miniplates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels un… more
Date: March 7, 2002
Creator: Travelli, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Study of diffusion bond development in 6061 aluminum and its relationship to future high density fuels fabrication.

Description: Powder metallurgy dispersions of uranium alloys and silicides in an aluminum matrix have been developed by the RERTR program as a new generation of proliferation-resistant fuels. Testing is done with miniplate-type fuel plates to simulate standard fuel with cladding and matrix in plate-type configurations. In order to seal the dispersion fuel plates, a diffusion bond must exist between the aluminum coverplates surrounding the fuel meat. Four different variations in the standard method for roll-… more
Date: October 7, 1997
Creator: Prokofiev, I.; Wiencek, T. & McGann, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The RERTR program.

Description: The Reduced Enrichment Research and Test Reactor (RERTR) Program was established in 1978 at the Argonne National Laboratory (ANL) by the Department of Energy (DOE), which continues to fund the program and to manage it in coordination with the Department of State (DOS), the Arms Control and Disarmament Agency (ACDA), and the Nuclear Regulatory Commission (NRC). The primary objective of the program is to develop the technology needed to use Low-Enrichment Uranium (LEU) instead of High-Enrichment … more
Date: November 14, 1997
Creator: Travelli, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Neutronic safety parameters and transient analyses for potential LEU conversion of the Budapest Research Reactor.

Description: An initial safety study for potential LEU conversion of the Budapest Research Reactor was completed. The study compares safety parameters and example transients for reactor cores with HEU and LEU fuels. Reactivity coefficients, kinetic parameters and control rod worths were calculated for cores with HEU(36%) UAl alloy fuel and UO{sub 2}-Al dispersion fuel, and with LEU (19.75%)UO{sub 2}-Al dispersion fuel that has a uranium density of about 2.5 g/cm{sup 3}. A preliminary fuel conversion plan wa… more
Date: September 27, 1999
Creator: Pond, R. B.; Hanan, N. A.; Matos, J. E. & Maraczy, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Photon dose rates from spent fuel assemblies with relation to self-protection (Rev. 1)

Description: Photon dose rates as a function of fission product decay times have been calculated for spent fuel assemblies typical of MTR-type research and test reactors. Based upon these dose rates, the length of time that a spent fuel assembly will be self-protecting (dose rate greater than 100 rem/h at 1 m in air) can be estimated knowing the mass of fuel burned, the fraction of fuel burned, and the fuel assembly specific power density.
Date: February 1, 1996
Creator: Pond, R. B. & Matos, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some Tooling for Manufacturing Research Reactor Fuel Plates

Description: This paper will discuss some of the tooling necessary to manufacture aluminum-based research reactor fuel plates. Most of this tooling is intended for use in a high-production facility. Some of the tools shown have manufactured more than 150,000 pieces. The only maintenance has been sharpening. With careful design, tools can be made to accommodate the manufacture of several different fuel elements, thus, reducing tooling costs and maintaining tools that the operators are trained to use. An impo… more
Date: October 3, 1999
Creator: Knight, R.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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US-RERTR Advanced Fuel Development Plans : 1999.

Description: Twelve fuel alloys were included in the very-high-density RERTR-1 and RERTR-2 microplate irradiation experiments. Experience gained during fabrication and results from the post-irradiation examination of these fuels has allowed us to narrow the focus of our fuel development efforts in preparation for the next set of irradiation experiments. Specific technical problems in both the areas of fuel fabrication and irradiation performance remain to be addressed. Examples of these are powder fabricati… more
Date: October 22, 1998
Creator: Meyer, M. K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Final Site Specific Decommissioning Inspection Report #2 for the University of Washington Research and Test Reactor, Seattle, Washington

Description: During the period of August through November 2006, ORISE performed a comprehensive IV at the University of Washington Research and Test Reactor Facility. The objective of the ORISE IV was to validate the licensee’s final status survey processes and data, and to assure the requirements of the DP and FSSP were met.
Date: March 20, 2007
Creator: Roberts, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

RERTR-6 Irradiation Summary Report

Description: The Reduced Enrichment for Research and Test Reactor (RERTR) experiment RERTR-6 was designed to evaluate several modified fuel designs that were proposed to address the possibility of breakaway swelling due to porosity within the (U. Mo) Al interaction product observed in the full-size plate tests performed in Russia and France1. The following report summarizes the life of the RERTR-6 experiment through end of irradiation, including as-run neutronic analyses, thermal analyses and hydraulic test… more
Date: December 1, 2011
Creator: Perez, D. M.; Lillo, M. A.; Chang, G. S.; Roth, G. A.; Woolstenhulme, N. E. & Wachs, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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