Radiation Enhanced Diffusion in Nuclear Carbides

  • Hj. Matzke
Part of the NATO ASI Series book series (NSSB, volume 129)

Abstract

The radiation enhanced diffusion (coefficient D*) of Pu-238 and U-233 in polycrystalline and single crystalline UC and in sintered (U,Pu)C with 3 and 15 % Pu was measured in a nuclear reactor during fission. Conventional diffusion sandwiches with thin tracer layers and a RF furnace for temperature variation (130 to 1400 °C) were used. D* was found to be completely athermal below 1100 °C and to increase linearly with fission rate, \(\dot F\), according to D* =A\(\dot F\) with A = (2.5±0.5) × 10−30cm5. The mechanism of enhancement is discussed as well as the implications on technologically important processes. The results are related to recent fission damage studies and compared with those obtained on other nuclear fuels, UO2 and UN.

Keywords

Porosity Furnace Carbide Depression Welding 

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Copyright information

© Plenum Press, New York 1985

Authors and Affiliations

  • Hj. Matzke
    • 1
  1. 1.Commission of the European Communities Joint Research Centre, Karlsruhe EstablishmentEuropean Institute for Transuranium ElementsKarlsruheFederal Republic of Germany

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