Studies of Mo-99 separation from uranium solution using alumina as a sorbent

Objectives A rapid and efficient method of Mo-99 separation obtained by fission of U-235 requires a continous improvement.

Methods Adsorption of Mo on alumina filled columns is an atractive process due to its simplicity. Radioactive impurities will be measure by gamma spectrometry.

Results A separation yield as a function of solution pH, uranium concentation and flow rate has been studied in detail. The desorption of molybdenum and its purification from some fission products will also be presented.

Conclusions Results will be used in small scale production of Mo-99.

Research Support Polish Government grant