Collection of uranium by polyurethane foam loaded with LIX 63

Recovery of uranium(VI) from dilute solutions by the use of the open-cell polyurethane foam (PUF) loaded with 5,8-diethyl-7-hydroxy-6-dodecanone oxime (LIX 63) has been investigated. Above pH 4.5 more than 99 % of the uranium in the solutions was sorbed onto the LIX 63 loaded PUF. The sorbed uranium was recovered from the PUF with dilute acid solutions, and the loaded PUF could be repeatedly used in a batch or column method. The sorption of uranium was accelerated by squeezing the PUF and by increasing temperature. The sorption capacity for uranium increases linearly with an increase in LIX 63 loading the PUF. Quantitative collection of uranium over a relatively wide range of concentrations can be achieved, provided that the PUF contains an excess of LIX 63. (author)