Investigation of physico-mechanical properties of ceramic oxide kernels for nuclear applications

Titov, M M; Fachinger, J.; Bukaemskiy, Andrey

doi:10.1016/j.jnucmat.2004.03.001

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2006

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“…For leaching experiments in salt brines, uranium was preliminarily separated from aliquots by solid phase extraction using Eichrom UTEVA resin in nitric acid media. The evolution of the fuel kernels surfaces was analysed by SEM after the static experiments (Titov et al, 2004). Flow-through leaching tests were performed under reducing conditions at ambient temperature with MOX fuel kernels (Th 0.977 ,U 0.023 )O 2 and (Th 0.906 ,U 0.094 )O 2 , (Th 0.834 ,U 0.166 )O 2 in synthetic clay groundwater (see Table 6).…”

Section: Methodsmentioning

confidence: 99%