Cyclotron production of 225Ac from an electroplated 226Ra target

Purpose We demonstrate cyclotron production of high-quality 225Ac using an electroplated 226Ra target. Methods 226Ra was extracted from legacy Ra sources using a chelating resin. Subsequent ion-exchange purification gave pure 226Ra with a certain amount of carrier Ba. The radium target was prepared by electroplating. We successfully deposited about 37 MBq of 226Ra on a target box. Maximum activation was achieved using 15.6 MeV protons on the target at 20 µA for 5 h. Two functional resins with various concentrations of nitric acid purified 225Ac and recovered 226Ra. Cooling the intermediate 225Ac for 2–3 weeks decayed the major byproduct of 226Ac and increased the radionuclidic purity of 225Ac. Repeating the same separation protocol provided high-quality 225Ac. Results 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. Additional cooling time coupled with the separation procedure (secondary purification) effectively increased the 225Ac (4n + 1 series) radionuclidic purity up to 99 + %. The recovered 225Ac had a similar identification to commercially available 225Ac originating from a 229Th/225Ac generator. Conclusion 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.

Cyclotron Production of 225Ac from an electroplated 226Ra Target

Purpose We demonstrate a cyclotron production of high-quality 225Ac using an electroplated 226Ra target. Methods All 226Ra used in this work was extracted from legacy Ra sources using a chelating resin. The subsequent ion-exchange purification gave pure 226Ra with a certain amount of carrier Ba. The radium target was prepared by electroplating. We successfully deposited about 1 mg (mCi) of 226Ra on a target box. Activation was performed by 16.5 MeV protons (on the target) at 20 µA for 5 h as the maximum. Purification of 225Ac as well as 226Ra recovery was performed using two functional resins with various concentrations of nitric acid. Cooling of the intermediate 225Ac for 2–3 weeks decayed the major byproduct of 226Ac and increased the radionuclidic purity of 225Ac. Then the same separation protocol was repeated to provide high-quality 225Ac. Results We obtained 225Ac at a yield of about 2.4 MBq (65 µCi) at EOB, and the subsequent primal purification gave 1.7 MBq (48 µCi) of 225Ac with 226Ac/225Ac ratio of < 4% at 4 d from EOB. Additional cooling time coupled with the repeated separation procedure (secondary purification) effectively increased the 225Ac (4n + 1 series) radionuclidic purity up to 99+%, which showed a similar identification to a commercially available 225Ac originating from a 229Th/225Ac generator. Conclusion The 226Ra(p,2n)225Ac reaction and the appropriate purification procedure has the potential to be a major alternative pathway for 225Ac production and can be performed in any facility with a compact cyclotron to address the increasing demand for 225Ac.

Development of 186/188Re-Chitosan as an Effective Therapeutic Agent for Rheumatoid Arthritis

Background: Rheumatoid arthritis (RA) is an inflammatory chronic disease characterized by inflammation, pain, swelling and disability and radiosynovectomy is one of the disease treatment lines. In this study, the possibility of providing rhenium-186/rhenium-188 chitosan radiopharmaceuticals, optimization of conditions for their production and bio-distribution. Objective: In order to build perrhenic acid for labeling, natural rhenium was exposed to radiation. Radionuclidic and radiochemical purities of (186/188Re)-NaReO4 were examined by gamma spectroscopy and paper chromatography methods, respectively. Methods: Labeling of chitosan with rhenium was done in different acidic situations. The radiochemical purity 186/188Re-chitosan was applied by radio thin layer chromatography (RTLC). Lastly, the bio-distribution of the radiolabeled chitosan was studied in various organs after intra articular injection of the complex to lab rats. Gamma spectrometry confirmed the high rhenium radionuclidic purity. Chromatography results showed that perrhenic acid was produced with purity greater than 97% and rhenium chitosan labeling was done over 98% in pH = 3. Dissection results showed high bio-distribution of 186/188Re-chitosan after injection into the joint with no leakage to surrounding organs. Conclusion: According to the results, there is a possibility of labeling rhenium with chitosan in very high radiochemical purity. Regarding the high retention of these radiopharmaceuticals in joints with no leakage to surrounding organs, 186/188Re-chitosan can be applied as new radiosynovectomy drugs for rheumatoid arthritis treatment.

Quality assurance of Mo-99/Tc-99m radionuclide generators

Gamma-ray spectrometry analyses of the radionuclide content of eluate from two Mo-99/Tc-99m radionuclide generators POLTECHNET have been performed. The relative activities of 99Mo 103Ru and 131I radioisotopes with respect to the activity of 99mTc at different time intervals after the primary pertechnetate elution of the generators have been analyzed. The relative activities of the isotopes were determined and compared to the radionuclidic purity requirements for 99mTc.