Crystallographic study of Si and ZrN coated U–Mo atomised particles and of their interaction with al under thermal annealing

A new type of high density fuel is needed for the conversion of research and test reactors from high to lower enriched uranium. The most promising one is a dispersion of atomized uranium-molybdenum (U–Mo) particles in an Al matrix. However, during in-pile irradiation the growth of an interaction lay...

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Veröffentlicht in:Journal of nuclear materials 2013-11, Vol.442 (1-3), p.124-132
Hauptverfasser: Zweifel, T., Palancher, H., Leenaers, A., Bonnin, A., Honkimaki, V., Tucoulou, R., Van Den Berghe, S., Jungwirth, R., Charollais, F., Petry, W.
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Sprache:eng
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