Bench scale experiment of the TRPU process for the removal of actinide elements from high level radioactive waste

In this paper the TRPO process for the removal of actinide elements from high level radioactive waste (HAW) is verified by multistage counter current Bench-scale experiments with synthetic HAW solution. In order to improve neptunium removed efficiency its valence is adjusted to Np(IV) by electrolytic reduction. When nitric acid concentration of feed solution is 1 mol/L. more than 99.9% Am. Pu. Np. and U are recovered from synthetic HAW Solution by a few stages extraction with 30% TRPO-Kerosene. The striping of actinides loaded in TRPO are accomplished by nifric acid, oxalic acid and sodium carbonate. The stripped actinide are divided into three groups: Am + RE. Np - Pu and U. Cross contamination between these groups is very little. The behavior of F.P. elements in the process are also investigated. The relative distribution of actinides and F.P elements in the process streams solutions are given. The experimental Concentration profiles of Am. and NMO are in good accordance with the calculated ones by using simulated mathematic model