Ion-exchange materials are routinely used in radioisotope separations and in medical isotope generators. In this study we examined the poorly crystalline silicotitanate (PCST) for the separation of 113Sn from 113mIn. 113Sn (t1/2=115 days) decays to 113mIn (t1/2=99.6 min) of interest for medical imaging. Kd studies of PCST in 0.1M acetate buffers from pH 1-5 indicated the material had high affinity of Sn and low affinity of In at pH 3 and could be used in a separation and/or generator. A 0.6 ml PCST column was prepared in 0.1 M ammonium acetate at pH 3, and ~15 µCi of 113Sn was loaded on the material. The loading, 113In yield and 113Sn breakthrough was quantified by gamma spectroscopy. Initial 113mIn yield was 76% within the first 3ml of eluant. After ten fractions collected over 1 month, the elution profile broadened, and the 113mIn yield decreased to below 10% in a 10 ml volume. A decrease in the flow rate through the PCST column was observed near the end of the trial. Breakdown of the PCST material was evaluated by measuring titanium by ICP-OES and compared to a control study with no radioactivity. Titanium measured in the first elution was 2.6 µg and increased to 24.6 µg by the tenth elution. The elution profile of titanium on a similar column without radioactivity produced 1% the Ti mass per elution and did not exhibit a decrease in flow rate. Studies indicate PCST could separate Sn from In, but the material contained titanium as a result of column degradation, decreased flow rate, reduced 113mIn yield and broadened elution profile. The data indicates that an engineered form of the material is needed to achieve better performance as generator support.

Evaluation of PCST ion exchange material for a Sn-113/In-113m generator

Macromolecular Chemistry: The Second Century

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ACS Spring 2020 National Meeting & Expo

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