Ion-Exchange Selectivity of Tertiary Pyridine-Type Anion-Exchange Resin for Treatment of Spent Nuclear Fuels

Abstract

The tertiary pyridine-type anion-exchange resin has been synthesized for the treatment of spent nuclear fuels and high-level radioactive waste. This resin, with a uniform diameter of 60 µm, is mechanically strong enough and shows no swelling or shrinking regardless of its chemical forms. Systematic analysis was made of the adsorption selectivities of the resin in HCl solutions for a number of cations that exist in spent fuels, such as uranium and fission product elements. The results indicate that the resin is suitable to be used for the treatment of spent fuels and high-level radioactive waste.