![]() ![]() ![]() Consequently, few facilities can practically produce 225Ac via the spallation route. However, the reaction requires a projectile with an extraordinarily high energy and intensity (e.g., 100 MeV or higher proton). Among these, option (1) holds promise because 232Th is not a fissile material according to nuclear regulations. Practical options include (1) high-energy protons on 232Th (spallation channel, ), (2) moderate energy protons on 226Ra (nuclear transmutation channel, ), and (3) high-intensity gammas on 226Ra (photonuclear/Bremsstrahlung channel, ). Many studies have investigated increasing actinium-225 production to meet the anticipated demand. Consequently, alternative production pathways are highly desired. However, only a few institutes such as the Joint Research Centre (JRC, Karlsruhe, Germany), Oak Ridge National Laboratory (ORNL, TN, USA), and the Institute of Physics and Power Engineering (IPPE, Kaluga Oblast, Russia) have such capabilities and their estimated total annual capacity of actinium-225 is approximately 63 GBq (1.7 Ci). Currently, the most realistic path is the natural decay product by a 229Th/ 225Ac generator system. A shortage of actinium-225 is anticipated because interest has drastically increased but large-scale commercial production is still in the development phase. ![]() The former is typically used to produce short-lived isotopes, while the latter is used for large-scale, centralized production. Both accelerators and nuclear reactors are used to produce medical-grade isotopes. The accessibility of various radioisotopes for diagnostic nuclear medicine is well established. This procedure, which involves the 226Ra(p,2n) 225Ac reaction and the appropriate purification, has the potential to be a major alternative pathway for 225Ac production because it can be performed in any facility with a compact cyclotron to address the increasing demand for 225Ac. The recovered 225Ac had a similar identification to commercially available 225Ac originating from a 229Th/ 225Ac generator. Additional cooling time coupled with the separation procedure (secondary purification) effectively increased the 225Ac (4n + 1 series) radionuclidic purity up to 99 + %. We obtained 225Ac at a yield of about 2.4 MBq at the end of bombardment (EOB), and the subsequent initial purification gave 1.7 MBq of 225Ac with 226Ac/ 225Ac ratio of < 3% at 4 days from EOB. Repeating the same separation protocol provided high-quality 225Ac. Cooling the intermediate 225Ac for 2–3 weeks decayed the major byproduct of 226Ac and increased the radionuclidic purity of 225Ac. Two functional resins with various concentrations of nitric acid purified 225Ac and recovered 226Ra. Maximum activation was achieved using 15.6 MeV protons on the target at 20 ♚ for 5 h. We successfully deposited about 37 MBq of 226Ra on a target box. The radium target was prepared by electroplating. Subsequent ion-exchange purification gave pure 226Ra with a certain amount of carrier Ba. MethodsĢ26Ra was extracted from legacy Ra sources using a chelating resin. We demonstrate cyclotron production of high-quality 225Ac using an electroplated 226Ra target. ![]()
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