Behavior of Zircaloy Cladding in the Presence of Gallium

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The U.S. Department of Energy has established a dual-track approach to the disposition of plutonium arising from the dismantling of nuclear weapons. Both immobilization and reactor-based mixed-oxide (MOX) fuel technologies are being evaluated. The reactor-based MOX fuel option requires assessment of the potential impact of concentrations of gallium (on the order of 1 to 10 ppm), not present in conventional MOX fuel, on cladding material performance. An experimental program was designed to evaluate the performance of prototypic Zircaloy cladding materials against (1) liquid gallium, and (2) various concentrations of G~03. Three types of tests were performed: (1) corrosion, (2) liquid ... continued below

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13 Pages

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DiStefano, J.R.; King, J.F.; Manneschmidt, E.T.; Strizak, J.P. & Wilson, D.F. September 28, 1998.

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Description

The U.S. Department of Energy has established a dual-track approach to the disposition of plutonium arising from the dismantling of nuclear weapons. Both immobilization and reactor-based mixed-oxide (MOX) fuel technologies are being evaluated. The reactor-based MOX fuel option requires assessment of the potential impact of concentrations of gallium (on the order of 1 to 10 ppm), not present in conventional MOX fuel, on cladding material performance. An experimental program was designed to evaluate the performance of prototypic Zircaloy cladding materials against (1) liquid gallium, and (2) various concentrations of G~03. Three types of tests were performed: (1) corrosion, (2) liquid metal embrittlement, and (3) corrosion-mechanical. These tests were to determine corrosion mechanisms, thresholds for temperature and concentration of gallium that delineate behavioral regimes, and changes in the mechanical properties of Zircaloy. Results have generally been favorable for the use of weapons-grade (WG) MOX fhel. The Zircaloy cladding does react with gallium to form intermetallic compounds at >3000 C; however, this reaction is limited by the mass of gallium and is therefore not expected to be significant with a low level (parts per million) of gallium in the MOX fuel. Furthermore, no evidence for grain boundary penetration by gallium or liquid metal embrittlement was observed.

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13 Pages

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  • OECD/NEA Workshop on Physics and Fuel Performance, Paris, France, Sept. 28-30, 1998

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  • Other: DE00002952
  • Report No.: ORNL/CP-100699
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 2952
  • Archival Resource Key: ark:/67531/metadc678671

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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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  • September 28, 1998

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  • July 25, 2015, 2:20 a.m.

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  • Nov. 17, 2015, 10:03 a.m.

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DiStefano, J.R.; King, J.F.; Manneschmidt, E.T.; Strizak, J.P. & Wilson, D.F. Behavior of Zircaloy Cladding in the Presence of Gallium, article, September 28, 1998; United States. (digital.library.unt.edu/ark:/67531/metadc678671/: accessed September 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.