Abstract
Technetium is part of the fission products of uranium formed during the operation of a nuclear reactor. The accumulation of technetium in the fuel is about 1090 g/t-U with a burn up of 40 GW day/t-U. The half-life of Tc-99 is 212 thousand years and its removal into radioactive waste together with relatively short-lived (T1/2 = 30–50 years), the handling of which implies near-surface storage, seems unacceptable. In view of this, it is advisable to remove Tc from the 1st cycle raffinate before concentrating and solidifying. All known variants of Tc isolation are based on its ability to complexate with TBP with subsequent extraction, as well as to co-extract in anionic form with U (VI) and tetravalent elements. To this end, we studied the effect of zirconium (VI) concentration on the extraction of technetium (VII) in the processing of spent nuclear fuel (SNF).
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