Technetium Recovery from Uranium Extract and Its Concentration Using a Separator during Reprocessing of Spent Nuclear Fuel
摘要
Abstract
The process of reductive reextraction of technetium from a simulated solution of spent nuclear fuel using a separator equipped with an upper separation chamber was tested. Technetium-concentrating reextraction was performed using a nitric acid solution containing a mixture of the reductants carbohydrazide and diformylhydrazine at an organic-to-aqueous (O/A) phase ratio of 20 to 25. Precipitation was observed during reextraction, but it did not disturb the hydrodynamic operating conditions of the separator.