Reactor production of promethium-147
In this paper, we describe the 147 Pm production yields and level of impurities from several targets that consisted of milligram quantities of highly enriched 146 Nd oxide irradiated at the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory for durations ranging from 24 to180 h. A comparison between theoretical and experimental data are also presented, and attempts were made to empirically evaluate the neutron capture cross-sections of 41.3-d 148m Pm and 5.4-d 148g Pm. For a one-cycle irradiation (~24 days), 147 Pm yield reaches a maximum value of 101.8 MBq/mg (2.75 mCi/mg) at 60 days after the end of bombardment. Because of large neutron capture cross-sections of 147 Pm, the yield of 147 Pm does not significantly increase with longer irradiation. Our estimates of the thermal neutron capture cross-section and resonance integral for 146 Nd at 1.48 ± 0.05 b and 2.56 ± 0.25 b, respectively, were consistent with the reported values. The effective neutron capture cross-section of 147 Pm to 148m Pm was 53.3 ± 2.7 b - a factor of 2 lower than the 98.7 ± 6.5 b calculated from reported cross-sections. The measured σ eff to the ground state (5.37-d 148g Pm) was 82.0 ± 4.1 b; ~34 % lower than the value of 139 ± 0 b calculated from reported cross-sections. In this work, we also describe the development of a chemical process based on extraction and ion-exchange chromatography for separation of 147 Pm from milligram quantities of 146 Nd and other impurities. Sequential separation of Pm from the Nd target and from other radioisotopic impurities ( 153 Gd and 154&155 Eu, 192 Ir, and 60 Co) was achieved using a LN extraction resin in HCl media followed by further purification of Pm from 60 Co and 192 Ir using a low cross-linking cation exchange resin. Based on these data, we estimated that two rounds of purification under our experimental conditions can provide a mass separation factor of > 104 between Pm and Nd. Our data indicate that curie quantities of 147 Pm with suitable chemical and radioisotopic purity for applications in beta voltaic batteries can be produced by irradiating gram quantities of highly enriched 146 Nd in the flux trap of HFIR for one cycle.