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Sintering particulars of pelletized oxide nuclear fuel

Baranov, V. ; Kuzmin, R. ; Tenishev, A. ; Khlunov, A. ; Ivanov, A. ; Petrov, I. ; Timoshin, I.

Atomic Energy, 2011, Vol.110(3), pp.172-177 [Periódico revisado por pares]

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  • Título:
    Sintering particulars of pelletized oxide nuclear fuel
  • Autor: Baranov, V. ; Kuzmin, R. ; Tenishev, A. ; Khlunov, A. ; Ivanov, A. ; Petrov, I. ; Timoshin, I.
  • Assuntos: Sintering ; Nuclear Industry ; Lubricants ; Nuclear Energy
  • É parte de: Atomic Energy, 2011, Vol.110(3), pp.172-177
  • Descrição: Sintering of oxide nuclear fuel pellets has been studied by dilatometric and thermogravimetric studies in the medium Ar–8%H 2 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.
  • Idioma: Inglês

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