Journal of Nuclear Fuel Cycle and Waste Technology

Alpha spectrometry was studied for the determination of 237Np in spent nuclear fuel samples. The optimum condition for the electrodeposition of 237Np was obtained as follows : for 1 1.5 hour of deposition time, at the current intensity of 1.2 1.5 A and at sodium sulfate electrolyte without organic additive. The deposition yield and its reproducibility on 237Np was decreased as the amount of 237Np decreased from 4.16 Bq down to 0.0264 Bq(1ng). The recovery yield of 237Np determined by alpha spectrometry after separation in synthetic solution was 98.8±5.1%(n=4). The contents of 237Np in spent nuclear fuel samples were determined and the result showed an agreement within 10% of a difference between the measurement and the calculation.

Keywords

237Np,alpha spectrometry,electrodeposition,anion exchange chromatography,actinides separation