Sequential cation-exchange separation of molybdenum-99 and tellurium-132 from neutron irradiated U3O8.

概要

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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.
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