Cermet fuel for fast reactor – Fabrication and characterization

(U, Pu)O2 ceramic fuel is the well-established fuel for the fast reactors and (U, Pu, Zr) metallic fuel is the future fuel. Both the fuels have their own merits and demerits. Optimal solution may lie in opting for a fuel which combines the favorable features of both fuel systems. The choice may be t...

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Veröffentlicht in:Journal of nuclear materials 2013-11, Vol.442 (1-3), p.400-407
Hauptverfasser: Mishra, Sudhir, Kutty, P.S., Kutty, T.R.G., Das, Shantanu, Dey, G.K., Kumar, Arun
Format: Artikel
Sprache:eng
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Zusammenfassung:(U, Pu)O2 ceramic fuel is the well-established fuel for the fast reactors and (U, Pu, Zr) metallic fuel is the future fuel. Both the fuels have their own merits and demerits. Optimal solution may lie in opting for a fuel which combines the favorable features of both fuel systems. The choice may be the use of cermet fuel which can be either (U, PuO2) or (Enriched U, UO2). In the present study, attempt has been made to fabricate (Natural U, UO2) cermet fuel by powder metallurgy route. Characterization of the fuel has been carried out using dilatometer, differential thermal analyzer, X-ray diffractometer, and Scanning Electron Microscope. The results show a high solidus temperature, high thermal expansion, presence of porosities, etc. in the fuel. The thermal conductivity of the fuel has also been measured. X-ray diffraction study on the fuel compact reveals presence of α U and UO2 phases in the matrix of the fuel.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2013.08.051