Separation of Transuranium Elements from High-Activity Wastes of Reprocessing of Nuclear Fuels

摘要

In order to evaluate the performances required for this separation, calculations have been made by taking into account the properties of the glass designed to confine the wastes and values of the CMA for the various isotopes concerned. Although separation by precipitation cannot be refected a priori, we have directed our efforts towards solvent extraction. Various schemes have been considered. (ERA citation 04:007512)