Determination of 63Ni and 59Ni in spent ion-exchange resin and activated charcoal from the IEA-R1 nuclear research reactor

A radiochemical method has been adapted to determine 59Ni and 63Ni in samples of radioactive wastes from the water cleanup system of the IEA-R1 nuclear research reactor. The process includes extraction chromatographic resin with dimethylglyoxime (DMG) as a functional group. Activity concentrations of 59Ni and 63Ni were measured, respectively, by X-ray spectrometry and liquid scintillation counting, whereas the chemical yield was determined by ICP-OES. The average ratio of measured activity concentrations of 63Ni and 59Ni agree well with theory.

► A radiochemical method was adapted for determination of 59Ni and 63Ni.
► 59Ni and 63Ni were determined in samples of radioactive wastes from research reactor.
► The activity concentration of 59Ni was measured by X-ray spectrometry.
► The activity concentration of 63Ni was measured by liquid scintillation counting.
► Average ratio of measured activity concentrations of 63Ni and 59Ni agrees with theory.