Thermochemical Analysis of Gas-Cooled Reactor Fuels Containing Am and Pu Oxides

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Description

Literature values and estimated data for the thermodynamics of the actinide oxides and fission products are applied to explain the chemical behavior in gas-cooled-reactor fuels. Emphasis is placed on the Am-O-C and Pu-O-C systems and the data are used to plot the oxygen chemical potential versus temperature of solid-solid and solid-gas equilibria. These results help explain observations of vaporization in Am oxides, nitrides, and carbides and provide guidance for the ceramic processing of the fuels. The thermodynamic analysis is then extended to the fission product systems and the Si-C-O system. Existing data on oxygen release (primarily as CO) as a ... continued below

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52 pages

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Lindemer, T. B. September 5, 2002.

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Description

Literature values and estimated data for the thermodynamics of the actinide oxides and fission products are applied to explain the chemical behavior in gas-cooled-reactor fuels. Emphasis is placed on the Am-O-C and Pu-O-C systems and the data are used to plot the oxygen chemical potential versus temperature of solid-solid and solid-gas equilibria. These results help explain observations of vaporization in Am oxides, nitrides, and carbides and provide guidance for the ceramic processing of the fuels. The thermodynamic analysis is then extended to the fission product systems and the Si-C-O system. Existing data on oxygen release (primarily as CO) as a function of burnup in the thoria-urania fuel system is reviewed and compared to values calculated from thermodynamic data. The calculations of oxygen release are then extended to the plutonia and americia fuels. Use of ZrC not only as a particle coating that may be more resistant to corrosion by Pd and other noble-metal fission products, but also as a means to getter oxygen released by fission is discussed.

Physical Description

52 pages

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  • Other Information: PBD: 5 Sep 2002

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  • Report No.: ORNL/TM-2002/133
  • Grant Number: AC05-00OR22725
  • DOI: 10.2172/814208 | External Link
  • Office of Scientific & Technical Information Report Number: 814208
  • Archival Resource Key: ark:/67531/metadc733589

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Creation Date

  • September 5, 2002

Added to The UNT Digital Library

  • Oct. 18, 2015, 6:40 p.m.

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  • March 30, 2016, 6:19 p.m.

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Lindemer, T. B. Thermochemical Analysis of Gas-Cooled Reactor Fuels Containing Am and Pu Oxides, report, September 5, 2002; Tennessee. (digital.library.unt.edu/ark:/67531/metadc733589/: accessed September 26, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.