Abstract
A remotely operating polarograph was developed and a new polarographic method were established for the determination of uranium in waste of purex process.
The interference of dissolved organic solvent (TBP) was eliminated by adding ammonium sulfate (3.5 M) as a coagulator. Also, interfering nitrous acid was destroyed by urea.
The recommended procedure is as follows; In a polarographic cell, mix 500 μl of the sample solution and 5.0 ml of supporting electrolyte containing 3.5 M ammonium sulfate, 1M nitric acid and 0.1 M urea. After deareation with nitrogen for 15 minutes, d. c polarogram is recorded from -0.3 to -0.9 V vs. mercury anode. Uranium content is determined referring to a calibration curve.
For the synthetic waste solution containing of 9.0 × 10 -45 × 10-2 M uranium, the relative standard deviation was less than 2.5 per cent. Precision data for bench top as well as for the remote procedure showed no significant difference.
