An advanced ion exchange process for reprocessing spent nuclear fuels. Separation of real spent fuel solutions and conceptual design of the process

To develop an advanced aqueous reprocessing process using a minimal organic solvent and compact equipment to separate U, Pu and long-lived minor actinides from spent nuclear fuels, we have developed a new type of anion exchanger (AR-01) and several novel adsorbents containing a chelating ligand. A separation experiment for a nitric acid solution of spent BWR-fuel was demonstrated by an ion exchange column packed with AR-01. An advanced reprocessing process which consists of anion exchange as main separation method, electrolytic reduction for reducing U(VI) to U(IV) and extraction chromatography for Minor Actinides isolation has been designed and evaluated preliminarily. (author)