Journal of Nuclear Fuel Cycle and Waste Technology

Anion exchange chromatography and HDEHP extraction chromatography using DTPA-lactic acid as an eluent were applied in series for the separation of 241Am and 244Cm in radwaste samples. The separated elements were determined by electrodeposition at the sodium hydrogen sulfatesodium sulfate buffer solution followed by alpha-spectrometry. The recovery yields of 241Am and 244Cm were 85.2±17 % and 86.3±15.3 %, respectively, from the synthetic solution of spent nuclear fuel sample. The amounts of 241Am and 244Cm determined in radwaste sample solutions of condensate bottoms were at the range of 1.5 1.9 Bq/g and 1.7 Bq/g, respectively.

Keywords

241Am,244Cm,trans uranium,HDEHP extraction chromatography,electrodeposition,radwaste samples,alpha spectrometry