Uranium crystallization test with dissolver solution of irradiated fuel

Yano, Kimihiko ; Shibata, Atsuhiro  ; Nomura, Kazunori  ; Koizumi, Tsutomu; Koyama, Tomozo

The crystallization process has been developed as a part of the advanced aqueous process, NEXT (ew traction System for RU recovery) for fast reactor (FR) cycle. In this process, a large part of U is separated from dissolver solution by crystallization as UO(NO) 6HO. The U crystallization test was carried out with real dissolver solution of irradiated FR fuel to investigate the influence of cooling rate on the crystal size and the behavior of fission product (FP) compared with that of Pu(IV). In regard to the influence of the cooling rate, it was obvious that the crystal size was smaller as the cooling rate is faster. Although it was expectable that the decontamination performance was improved by diminishing the specific surface of the crystals, it was suggested that a large crystal produced by crystallization was not always high purity. Concerning the behavior of FPs, Eu behaved similarly to Pu(IV). Cs accompanied with U into the crystals under the condition in this test.