Sintering particulars of pelletized oxide nuclear fuel.

Autor: Baranov, V., Kuzmin, R., Tenishev, A., Khlunov, A., Ivanov, A., Petrov, I., Timoshin, I.
Předmět:
Zdroj: Atomic Energy; Jul2011, Vol. 110 Issue 3, p172-177, 6p
Abstrakt: Sintering of oxide nuclear fuel pellets has been studied by dilatometric and thermogravimetric studies in the medium Ar-8%H 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. [ABSTRACT FROM AUTHOR]
Databáze: Complementary Index