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A methodology based on the use of several separation/purification steps exploiting TOPO, Dowex anion exchanger and UTEVA for attaining U and Pu fractions for α-spectrometry measurements is presented. The methodology is applied to the determination of the concentration of  236 Pu and  232 U in a normal burn-up fuel (30 GWd/t) and in a high burn-up fuel (50 GWd/t). The results are compared with those from the calculations performed with the ORIGEN code.

radiochimica acta

Investigation of separation/purification methodologies for the determination of  232 U and  236 Pu in solution of spent nuclear fuels by α-spectrometry