Postirradiation examination of high-density uranium alloy dispersion fuels.

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Two irradiation test vehicles, designated RERTR-1 and RERTR-2, were inserted into the Advanced Test Reactor in Idaho in August 1997. These tests were designed to obtain irradiation performance information on a variety of potential new, high-density uranium alloy dispersion fuels, including U-10Mo,U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru and U-10Mo-0.05Sn; the intermetallic compounds U{sub 2}Mo and U{sub 3}Si{sub 2} were also included in the fuel test matrix. These fuels are included in the experiments as ''microplates'' (76 mm x 22 mm x 1.3 mm outer dimensions) with a nominal fuel volume loading of 25% and irradiated at relatively low ... continued below

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11 p.

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Hayes, S. L. October 28, 1998.

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Description

Two irradiation test vehicles, designated RERTR-1 and RERTR-2, were inserted into the Advanced Test Reactor in Idaho in August 1997. These tests were designed to obtain irradiation performance information on a variety of potential new, high-density uranium alloy dispersion fuels, including U-10Mo,U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru and U-10Mo-0.05Sn; the intermetallic compounds U{sub 2}Mo and U{sub 3}Si{sub 2} were also included in the fuel test matrix. These fuels are included in the experiments as ''microplates'' (76 mm x 22 mm x 1.3 mm outer dimensions) with a nominal fuel volume loading of 25% and irradiated at relatively low temperature ({approximately} 100 C). RERTR-1 and RERTR-2 were discharged from the reactor in November 1997 and July 1998, respectively, at calculated peak fuel burnups of 45 and 71 at.%-U{sup 235}. Both experiments are currently under examination at the Alpha Gamma Hot Cell Facility at Argonne National Laboratory in Chicago. This paper presents the postirradiation examination results available to date from these experiments.

Physical Description

11 p.

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OSTI as DE00011081

Medium: P; Size: 11 pages

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  • 21st International Meeting on Reduced Enrichment for Research and Test Reactors, Sao Paulo (BR), 10/18/1998--10/23/1998

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  • Report No.: ANL/ED/CP-97584
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11081
  • Archival Resource Key: ark:/67531/metadc620080

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  • October 28, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 7:42 p.m.

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Hayes, S. L. Postirradiation examination of high-density uranium alloy dispersion fuels., article, October 28, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc620080/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.