Sequential Cation-Exchange Separation of Molybdenum-99 and Tellurium-132 from Neutron Irradiated U₃O₈

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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 U₃O₈ 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 U₃O₈ in nitric acid and upon treatment of the solution with concentrated HCI. Relatively coarse particles of U₃O₈ were found more suitable for the present purpose of preparing ¹³²Te. Batches of U₃O₈ smaller than about 0.5 g proved to result in better separation of ⁹⁹Mo and ¹³²Te, for a column bed volume of 25 ml.