Influence of nitric acid and plutonium concentrations in dissolver solution of mixed oxide fuel on decontamination factors for uranyl nitrate hexahydrate crystal

摘要

In order to examine the decontamination behavior of the Pu and fission products (FPs) that contained with the uranyl nitrate hexahydrate (UNH) crystals in the U crystallization process, experiments were carried out using mixed oxide (MOX) fuel dissolver solution. The experiments confirmed that Eu was adequately decontaminated by washing the UNH crystals with a HNO 3 solution. However, Ba crystallized as Ba(NO_a)23nd the w_ashing was inefective for decontamination of Ba. High HNO_3and Pu concentrations in the mother liquor, the decontamination factor (DT) of Cs was low because Cs precipitated with Pu as Cs_.P)236 Tu(hNe_ OP_u clearly showed a reasonable DF because the amount of Pu in the dissolver solution was higher than that of Cs. Almost all the amount of Pu remains in the mother liquor except the one in the Cs_pP)236rue(cNi_pOit_ate.