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Sintering particulars of pelletized oxide nuclear fuel

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Sintering of oxide nuclear fuel pellets has been studied by dilatometric and thermogravimetric studies in the medium Ar–8%H2 at temperatures to 1600°C. Samples produced under commercial conditions using two different technologies were investigated: with the addition of a liquid plasticizer and alloying additives (wet technology) and by granulation and compaction (dry technology). It has been shown that sintering onset is characterized by the temperature interval 1100–1200°C for dry-technology pellets and 900–1000°C for wet-technology pellets. The pellets were sintered with different heating rates 1–8°C/min, and the dependence of the growth rate of the grains in sintered samples on the heat rate was determined. The mass losses of the samples were determined as a function of the temperature intervals tied to the release of the components of the lubricant and binder.

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Authors and Affiliations

  1. National Nuclear Research University – Moscow Engineering-Physics Institute (NIYaU MIFI), Moscow, Russia

    V. G. Baranov, R. S. Kuzmin, A. V. Tenishev & A. V. Khlunov

  2. Mashinostroitelnyi Zavod Company, Elektrostal, Moscow Oblast, Russia

    A. V. Ivanov, I. V. Petrov & I. S. Timoshin

Authors
  1. V. G. Baranov
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  2. R. S. Kuzmin
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  3. A. V. Tenishev
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  4. A. V. Khlunov
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  5. A. V. Ivanov
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  6. I. V. Petrov
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  7. I. S. Timoshin
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Additional information

Translated from Atomnaya Énergiya, Vol. 110, No. 3, pp. 146–149, March, 2011.

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Baranov, V.G., Kuzmin, R.S., Tenishev, A.V. et al. Sintering particulars of pelletized oxide nuclear fuel. At Energy 110, 172–177 (2011). https://doi.org/10.1007/s10512-011-9407-3

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  • DOI: https://doi.org/10.1007/s10512-011-9407-3

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