Abstract
A quantitative analytical method for the determination of the solubility of unirradiated (Pu, U)O 2 fuels is described below. The results indicate, that the solubility values are mainly depending on the processing variables, the densitiy of the MOX pellets, the time of dissolution and the concentration of the nitric acid. The definition of Pu-solubility for the standardised fuel specification and a suitable analytic procedure are still open to further discussions.
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