A comprehensive investigation of an approach for ¹⁴⁴Ce-separation as a by-product of the fission molybdenum-99 process

Cerium-144 (¹⁴⁴Ce), as a long-lived β emitter radioisotope (E_βavg = 82.25 keV, T_1/2 = 284.9 d), is a potentially promising radionuclide to be used in various medical and industrial applications. In this paper, an optimized process for the separation of ¹⁴⁴Ce from fission products is reported. Following the MCNPX calculation results, an equivalent solution was experimentally prepared that is similar to the waste solution of local ⁹⁹Mo production via the fission method. For analyzing the steps of the radiochemical process, the suitable radioisotope tracers created from the activation method and were added to the simulated waste solution. The oxidation/reduction potential of Ce³⁺/Ce⁴⁺ together with extraction chromatography was exploited to achieve high yields of more than 70% and a reasonable radionuclidic purity of 97% and radiochemical purity of more 99% of radiocerium.