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- Title
Sintering particulars of pelletized oxide nuclear fuel.
- Authors
Baranov, V.; Kuzmin, R.; Tenishev, A.; Khlunov, A.; Ivanov, A.; Petrov, I.; Timoshin, I.
- Abstract
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.
- Subjects
SINTERING; IRON metallurgy; OXIDES; NUCLEAR fuels; THERMOGRAVIMETRY; GRAVIMETRIC analysis; PLASTICIZERS
- Publication
Atomic Energy, 2011, Vol 110, Issue 3, p172
- ISSN
1063-4258
- Publication type
Article
- DOI
10.1007/s10512-011-9407-3