Irradiation testing of high density uranium alloy dispersion fuels

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Two irradiation test vehicles have been designed, fabricated, and inserted into the Advanced Test Reactor in Idaho. Irradiation of these experiments began in August 1997. These irradiation tests were designed to obtain irradiation performance information on a variety of potential new, high-density dispersion fuels. Each of the two irradiation vehicles contains 32 microplates. Each microplate is aluminum clad, having an aluminum matrix phase and containing one of the following compositions as the fuel phase: U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru, U-10Mo-0.05Sn, U{sub 2}Mo, or U{sub 3}Si{sub 2}. These experiments will be discharged at peak fuel burnups of ... continued below

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9 p.

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Hayes, S.L.; Trybus, C.L. & Meyer, M.K. October 1, 1997.

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Description

Two irradiation test vehicles have been designed, fabricated, and inserted into the Advanced Test Reactor in Idaho. Irradiation of these experiments began in August 1997. These irradiation tests were designed to obtain irradiation performance information on a variety of potential new, high-density dispersion fuels. Each of the two irradiation vehicles contains 32 microplates. Each microplate is aluminum clad, having an aluminum matrix phase and containing one of the following compositions as the fuel phase: U-10Mo, U-8Mo, U-6Mo, U-4Mo, U-9Nb-3Zr, U-6Nb-4Zr, U-5Nb-3Zr, U-6Mo-1Pt, U-6Mo-0.6Ru, U-10Mo-0.05Sn, U{sub 2}Mo, or U{sub 3}Si{sub 2}. These experiments will be discharged at peak fuel burnups of 40% and 80%. Of particular interest is the fission gas retention/swelling characteristics of these new fuel alloys. This paper presents the design of the irradiation vehicles and the irradiation conditions.

Physical Description

9 p.

Notes

INIS; OSTI as DE98050240

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  • 1997 international meeting on reduced enrichment for research and test reactors, Jackson Hole, WY (United States), 5-10 Oct 1997

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  • Other: DE98050240
  • Report No.: ANL/ED/CP--94198
  • Report No.: CONF-9710102--
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 658128
  • Archival Resource Key: ark:/67531/metadc712239

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • October 1, 1997

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  • Sept. 12, 2015, 6:31 a.m.

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  • May 16, 2016, 6:27 p.m.

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Hayes, S.L.; Trybus, C.L. & Meyer, M.K. Irradiation testing of high density uranium alloy dispersion fuels, article, October 1, 1997; United States. (digital.library.unt.edu/ark:/67531/metadc712239/: accessed December 10, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.