Cyclotron production of 68Ga in a liquid target: Effects of solution composition and irradiation parameters.

OBJECTIVES: To optimize 68Ga production using a liquid cyclotron target, investigations were performed to compare production yields using different concentrations of [68Zn]Zn(NO3)2, nitric acid, and irradiation parameters. METHODS: Different concentrations of [68Zn]Zn(NO3)2 (0.6 M, 1.2 M and 1.42 M) in varying normality of nitric acid (0.8-1.5 N) were prepared and irradiated with protons (incident energy ~14 MeV) using a BMLT-2 liquid target at different beam currents (30-50 µA) and irradiation times (30-60 min). The 68Ga production and saturation yields were calculated and compared. [68Ga]GaCl3 was isolated using in-house developed hydroxamate resin and optimized for routine application. Recycling of [68Zn]Zn(NO3)2 from the recovered target solution was also investigated. RESULTS: On increasing concentration of [68Zn]Zn(NO3)2 from 0.6 M to 1.2 M in 0.8 N nitric acid, decay corrected yield of 68Ga at EOB was found to be 1.64 GBq (44.4 mCi) and 3.37 GBq (91.0 mCi), respectively at 30 µA beam current, indicating production yield was proportional to zinc nitrate concentration for a 30 min irradiation. However, when beam current was increased to 40 µA while maintaining nitric acid concentration at 0.8 N, the proportional relationship of 68Zn-concentration with 68Ga production yield was lost [0.6 M, 2.29 GBq (61.9 mCi); 1.2 M, 3.6 GBq (97.3 mCi)] for a 30 min irradiation. In fact, the effect was more profound for 60 min irradiations [0.6 M, 2.96 GBq (80.0 mCi); 1.2 M, 4.25 GBq (115 mCi)]. Increasing nitric acid concentration to 1.25-1.5 N improved 68Ga production yield for 40 µA, 60-min irradiations (1.2 M; 5.17 GBq (140 mCi)). MP-AES analysis showed metal impurities as <0.20 µg Ga (n = 3), <0.93 µg Zn (n = 3) and < 2.7 µg Fe (n = 3). Based on above finding, 1.42 M [68Zn]Zn(NO3)2 in 1.2 N-HNO3 solutions were also studied to achieve highest production yields of 9.85 ±â€¯2.09 GBq (266 ±â€¯57 mCi) for 60 min irradiation at 40 µA beam current. After recycling,> 99% pure recycled [68Zn]zinc nitrate was obtained in 82.6 ±â€¯13.6% yield. CONCLUSIONS: 68Ga production yields were dependent on all four variables: concentrations of [68Zn]Zn(NO3)2 and nitric acid, beam current and duration of irradiation. Of note, increasing beam current and irradiation time may require increased concentrations of nitric acid to achieve expected increments in 68Ga production yield.

Improved production and processing of 89Zr using a solution target.

OBJECTIVE: The objectives of the present work were to improve the cyclotron production yield of (89)Zr using a solution target, develop a practical synthesis of the hydroxamate resin used to process the target, and develop a biocompatible medium for (89)Zr elution from the hydroxamate resin. METHODS: A new solution target (BMLT-2) with enhanced heat dissipation capabilities was designed by using helium-cooled dual foils (0.2 mm Al and 25 µ Havar) and an enhanced water-cooled, elongated solution cavity in the target insert. Irradiations were performed with 14 MeV protons on a 2M solution of yttrium nitrate in 1.25 M nitric acid at 40-µA beam current for 2 h in a closed system. Zirconium-89 was separated from Y by use of a hydroxamate resin. A one-pot synthesis of hydroxamate resin was accomplished by activating the carboxylate groups on a carboxymethyl cation exchange resin using methyl chloroformate followed by reaction with hydroxylamine hydrochloride. After trapping of (89)Zr on hydroxamate resin and rinsing the resin with HCl and water to release Y, (89)Zr was eluted with 1.2 M K2HPO4/KH2PO4 buffer (pH3.5). ICP-MS was used to measure metal contaminants in the final (89)Zr solution. RESULTS: The BMLT-2 target produced 349±49 MBq (9.4±1.2 mCi) of (89)Zr at the end of irradiation with a specific activity of 1.18±0.79 GBq/µg. The hydroxamate resin prepared using the new synthesis method showed a trapping efficiency of 93% with a 75 mg resin bed and 96-97% with a 100-120 mg resin bed. The elution efficiency of (89)Zr with 1.2M K2HPO4/KH2PO4 solution was found to be 91.7±3.7%, compared to >95% for 1 M oxalic acid. Elution with phosphate buffer gave very small levels of metal contaminants: Al=0.40-0.86 µg (n=2), Fe=1.22±0.71 µg (n=3), Y=0.29 µg (n=1). CONCLUSIONS: The BMLT-2 target allowed doubling of the beam current for production of (89)Zr, resulting in a greater than 2-fold increase in production yield in comparison with a conventional liquid target. The new one-pot synthesis of hydroxamate resin provides a simpler synthesis method for the (89)Zr trapping resin. Finally, phosphate buffer elutes the (89)Zrfrom the hydroxamate resin in high efficiency while at the same time providing a more biocompatible medium for subsequent use of (89)Zr.

Preparation and preliminary evaluation of 63Zn-zinc citrate as a novel PET imaging biomarker for zinc.

UNLABELLED: Abnormalities of zinc homeostasis are indicated in many human diseases. A noninvasive imaging method for monitoring zinc in the body would be useful to understand zinc dynamics in health and disease. To provide a PET imaging agent for zinc, we have investigated production of (63)Zn (half-life, 38.5 min) via the (63)Cu(p,n)(63)Zn reaction using isotopically enriched solutions of (63)Cu-copper nitrate. A solution target was used for rapid isolation of the (63)Zn radioisotope from the parent (63)Cu ions. Initial biologic evaluation was performed by biodistribution and PET imaging in normal mice. METHODS: To produce (63)Zn, solutions of (63)Cu-copper nitrate in dilute nitric acid were irradiated by 14-MeV protons in a low-energy cyclotron. An automated module was used to purify (63)Zn from (63)Cu in the target solution. The (63)Cu-(63)Zn mixture was trapped on a cation-exchange resin and rinsed with water, and the (63)Zn was eluted using 0.05 N HCl in 90% acetone. The resulting solution was neutralized with NaHCO3, and the (63)Zn was then trapped on a carboxymethyl cartridge, washed with water, and eluted with isotonic 4% sodium citrate. Standard quality control tests were performed on the product according to current good manufacturing practice, including radionuclidic identity and purity, and measurement of nonradioactive Zn(+2), Cu(+2), Fe(+3), and Ni(+2) by ion-chromatography high-performance liquid chromatography. Biodistribution and PET imaging studies were performed in B6.SJL mice after intravenous administration of (63)Zn-zinc citrate. (63)Cu target material was recycled by eluting the initial resin with 4N HNO3. RESULTS: Yields of 1.07 ± 0.22 GBq (uncorrected at 30-36 min after end of bombardment) of (63)Zn-zinc citrate were obtained with a 1.23 M (63)Cu-copper nitrate solution. Radionuclidic purity was greater than 99.9%, with copper content lower than 3 µg/batch. Specific activities were 41.2 ± 18.1 MBq/µg (uncorrected) for the (63)Zn product. PET and biodistribution studies in mice at 60 min showed expected high uptake in the pancreas (standard uptake value, 8.8 ± 3.2), liver (6.0 ± 1.9), upper intestine (4.7 ± 2.1), and kidney (4.2 ± 1.3). CONCLUSION: A practical and current good manufacturing practice-compliant preparation of radionuclidically pure (63)Zn-zinc citrate has been developed that will enable PET imaging studies in animal and human studies. (63)Zn-zinc citrate showed the expected biodistribution in mice.

Cyclotron production of (68)Ga via the (68)Zn(p,n)(68)Ga reaction in aqueous solution.

The objective of the present work is to extend the applicability of the solution target approach to the production of (68)Ga using a low energy cyclotron. Since the developed method does not require solid target infrastructure, it offers a convenient alternative to (68)Ge/(68)Ga generators for the routine production of (68)Ga. A new solution target with enhanced heat exchange capacity was designed and utilized with dual foils of Al (0.20 mm) and Havar (0.038 mm) separated by helium cooling to degrade the proton energy to ~14 MeV. The water-cooled solution target insert was made of Ta and its solution holding capacity (1.6 mL) was reduced to enhance heat transfer. An isotopically enriched (99.23%) 1.7 M solution of (68)Zn nitrate in 0.2 N nitric acid was utilized in a closed target system. After a 30 min irradiation at 20 µA, the target solution was unloaded to a receiving vessel and the target was rinsed with 1.6 mL water, which was combined with the target solution. An automated module was used to pass the solution through a cation-exchange column (AG-50W-X8, 200-400 mesh, hydrogen form) which efficiently trapped zinc and gallium isotopes. (68)Zn was subsequently eluted with 30 mL of 0.5 N HBr formulated in 80% acetone without any measurable loss of (68)Ga. (68)Ga was eluted with 7 mL of 3 N HCl solution with 92-96% elution efficiency. The radionuclidic purity was determined using an HPGe detector. Additionally, ICP-MS was employed to analyze for non-radioactive metal contaminants. The product yield was 192.5 ± 11.0 MBq/µ·h decay-corrected to EOB with a total processing time of 60-80 min. The radionuclidic purity of (68)Ga was found to be >99.9%, with the predominant contaminant being 67Ga. The ICP-MS analysis showed small quantities of Ga, Fe, Cu, Ni and Zn in the final product, with (68)Ga specific activity of 5.20-6.27 GBq/µg. Depending upon the user requirements, (68)Ga production yield can be further enhanced by increasing the (68)Zn concentration in the target solution and extending the irradiation time. In summary, a simple and efficient method of (68)Ga production was developed using low energy cyclotron and a solution target. The developed methodology offers a cost-effective alternative to the (68)Ge/(68)Ga generators for the production of (68)Ga.

Use of pressure-hold test for sterilizing filter membrane integrity in radiopharmaceutical manufacturing.

The bubble point test is the de facto standard for postproduction filter membrane integrity test in the radiopharmaceutical community. However, the bubble point test depends on a subjective visual assessment of bubbling rate that can be obscured by significant diffusive gas flows below the manufacturer's prescribed bubble point. To provide a more objective means to assess filter membrane integrity, this study evaluates the pressure-hold test as an alternative to the bubble point test. In our application of the pressure-hold test, the nonsterile side of the sterilizing filter is pressurized to 85% of the predetermined bubble point with nitrogen, the filter system is closed off from the pressurizing gas and the pressure is monitored over a prescribed time interval. The drop in pressure, which has a known relationship with diffusive gas flow, is used as a quantitative measure of membrane integrity. Characterization of the gas flow vs. pressure relationship of each filter/solution combination provides an objective and quantitative means for defining a critical value of pressure drop over which the membrane is indicated to be nonintegral. The method is applied to sterilizing filter integrity testing associated with the commonly produced radiopharmaceuticals, [(18)F]FDG and [(11)C]PIB. The method is shown to be robust, practical and amenable to automation in radiopharmaceutical manufacturing environments (e.g., hot cells).