Design of high density gamma-phase uranium alloys for LEU dispersion fuel applications.

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Uranium alloys are candidates for the fuel phase in aluminum matrix dispersion fuels requiring high uranium loading. Certain uranium alloys have been shown to have good irradiation performance at intermediate burnup. Previous studies have shown that acceptable fission gas swelling behavior and fuel-aluminum interaction is possible only if the fuel alloy can be maintained in the high temperature body-centered-cubic {gamma}-phase during fabrication and irradiation, i.e., at temperatures at which {alpha}-U is the equilibrium phase. Transition metals in Groups V through VIII are known to allow metastable retention of the gamma phase below the equilibrium isotherm. These metals have varying degrees ... continued below

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15 p.

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Hofman, G. L. October 19, 1998.

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Description

Uranium alloys are candidates for the fuel phase in aluminum matrix dispersion fuels requiring high uranium loading. Certain uranium alloys have been shown to have good irradiation performance at intermediate burnup. Previous studies have shown that acceptable fission gas swelling behavior and fuel-aluminum interaction is possible only if the fuel alloy can be maintained in the high temperature body-centered-cubic {gamma}-phase during fabrication and irradiation, i.e., at temperatures at which {alpha}-U is the equilibrium phase. Transition metals in Groups V through VIII are known to allow metastable retention of the gamma phase below the equilibrium isotherm. These metals have varying degrees of effectiveness in stabilizing the gamma phase. Certain alloys are metastable for very long times at the relatively low fuel temperatures seen in research reactor operation. In this paper, the existing data on the gamma stability of binary and ternary uranium alloys is analyzed. The mechanism and kinetics of decomposition of the gamma phase are assessed with the help of metal alloy theory. Alloys with the highest possible uranium content, good gamma-phase stability, and good neutronic performance are identified for further metallurgical studies and irradiation tests. Results from theory will be compared with experimentally generated data.

Physical Description

15 p.

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OSTI as DE00011061

Medium: P; Size: 15 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/TD/CP-97494
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11061
  • Archival Resource Key: ark:/67531/metadc619324

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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 19, 1998

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2017, 2:57 p.m.

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Hofman, G. L. Design of high density gamma-phase uranium alloys for LEU dispersion fuel applications., article, October 19, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc619324/: accessed December 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.