Radiological characterization of low-and intermediate-level radioactive wastes

An analytical procedure for the determination of activation products 238Pu, 241Pu, 239Pu/240Pu, 241Am, 237Np, and a fission product 90Sr in radioactive wastes is presented. Samples were decomposed using Fenton’s reaction. The separation was performed by anion-exchange chromatography, extraction chromatography, using TRU and Srresin, and precipitation techniques, followed by α-spectrometry and LSC counting. Tracer solutions and pure ion exchange resins were used to prepare artificial samples and trace nuclides during the analytical procedure. Some real samples of spent ion-exchange resins originating from our TRIGA Mark II research reactor were analyzed.