Development of a simple and selective separation of 67Cu from irradiated zinc for use in antibody labelling: A comparison of methods

The present and future of medical radionuclide production

“…They can all be produced at low-energy cyclotrons. Besides those four positron emitters, two other short-lived positron emitters, namely 68 15 O, in a few PET centres a small single particle cyclotron (E d < 4 MeV) has also been successfully utilized.…”

“…The product 123 Xe is removed from the NaI target, collected in a vessel and is allowed to decay for about 7 h. Thereafter 123 I is collected in a small volume by rinsing the inner wall of the vessel. This process leads to a high yield of 123 The above mentioned two less commonly used SPECT radionuclides, namely 67 Ga and 111 In, which are now also considered for Auger therapy (see below) are produced at a medium-sized cyclotron over the optimum energy range of E p = 25 → 18 MeV via the nuclear reactions 68 Zn( p, 2n) 67 Ga and 112 Cd( p, 2n) 111 In, respectively [cf . 4].…”

“…15]. The radionuclide 68 Ge is basically produced via the 69 Ga( p, 2n) 68 Ge reaction since the cross section is rather high (see discussion below). However, due to its long half-life, the yield is low and high proton beam fluxes approaching the mA level are essential.…”

“…As mentioned above, the production of the parent nuclides of the two commonly used generator-produced β + emitters, namely 68 Ga and 82 Rb, is done using intermediate energy reactions [cf . 15].…”

“…They comprise novel positron emitters and therapeutic radionuclides emitting low-range electrons and α-particles. The possible alternative production routes of a few established radionuclides, like 68 Ga and 99m Tc, are discussed. The status of standardisation of production data of the commonly used as well as of some emerging radionuclides is briefly mentioned.…”