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In the present work, we focused on determination of some important activation products like  238 Pu,  239 Pu/  240 Pu,  241 Am, and  237 Np, and  90 Sr as a fission product in spent ion exchange resins. The activation products of interest are alpha emitters, while  90 Sr is a beta emitter. Radioactive solutions of  241 Am,  238 Pu,  237 Np, and  90 Sr and pure ion exchange resins were used to prepare artificial samples which were subsequently subjected to an analytical procedure. This consisted of wet destruction of the resins with Fenton's reagent followed by separations using ion exchange. The activities found showed good agreement with calculated values and yields were also very good (above 50%). We also analysed five samples of spent ion exchange resin from the TRIGA Mark II research reactor. Activities of selected radionuclides were below expectations in all samples except in sample 1, which had higher activities of  90 Sr,  137 Cs,  60 Co,  152 Eu, and  154 Eu. Total beta/gamma activity did not exceed the max. permitted level for low level waste.

Determination of actinides and 90 Sr in spent ion exchange resins