The method of sequential cation-exchange separation of fission products proposed by Natsume
et al. was applied to the preparation of fission-produced
99Mo and
132Te, with particular attention paid to increasing the recovery of
99Mo and
132Te, and to reducing contamination with
95Zr-
95Nb and
103Ru. The cation-exchange behavior of these nuclides was found to be influenced by the particle size of the target U
3O
8 powder, the method of dissolution, the standing time allowed between dissolution and separation, and the quantity of uranyl ion treated in one batch. In order to enhance the distribution of
132Te in the Te fraction, and to reduce the contamination of the Mo and Te fractions with
95Zr-
95Nb and
103Ru, the ion-exchange separation should be applied immediately after dissolution of the U
3O
8 in nitric acid and upon treatment of the solution with concentrated HCI. Relatively coarse particles of U
3O
8 were found more suitable for the present purpose of preparing
132Te. Batches of U
3O
8 smaller than about 0.5 g proved to result in better separation of
99Mo and
132Te, for a column bed volume of 25 m
l.
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