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Fabrication and Irradiation Behavior of Uranium Mononitride

  • V. J. Tennery
  • T. N. Washburn
  • J. L. Scott
Conference paper
Part of the Materials Science Research book series (MSR, volume 5)

Abstract

Uranium mononitride is a candidate fuel for nuclear reactors for applications in space because of its high thermal conductivity, high fissile atom density, and dimensional stability at high temperature. High purity UN ceramics fabricated from nitride powders by uniaxial or isostatic pressing and sintered in nitrogen at temperatures ⩾2000°C, were irradiated at fuel temperatures to 1500°C and 2 w/c burnup. Results indicate no chemical reaction zone between fuel and metallic cladding, fuel swelling less than 2.8% Δ/V per atomic percent burnup, and maximum fission gas release of 7% of that generated.

Keywords

Rankine Cycle Fuel Pellet Nitride Powder Brayton Cycle Uranium Nitride 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Plenum Press, New York 1971

Authors and Affiliations

  • V. J. Tennery
    • 1
  • T. N. Washburn
    • 1
  • J. L. Scott
    • 1
  1. 1.Oak Ridge National LaboratoryOak RidgeUSA

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