66Ga: A Novelty or a Valuable Preclinical Screening Tool for the Design of Targeted Radiopharmaceuticals?

Emerging interest in extending the plasma half-life of small molecule radioligands warrants a consideration of the appropriate radionuclide for PET imaging at longer time points (>8 h). Among candidate positron-emitting radionuclides, 66Ga (t1/2 = 9.5 h, ß+ = 57%) has suitable nuclear and chemical properties for the labeling and PET imaging of radioligands of this profile. We investigated the value of 66Ga to preclinical screening and the evaluation of albumin-binding PSMA-targeting small molecules. 66Ga was produced by irradiation of a natZn target. 66Ga3+ ions were separated from Zn2+ ions by an optimized UTEVA anion exchange column that retained 99.99987% of Zn2+ ions and allowed 90.2 ± 2.8% recovery of 66Ga3+. Three ligands were radiolabeled in 46.4 ± 20.5%; radiochemical yield and >90% radiochemical purity. Molar activity was 632 ± 380 MBq/µmol. Uptake in the tumor and kidneys at 1, 3, 6, and 24 h p.i. was determined by µPET/CT imaging and more completely predicted the distribution kinetics than uptake of the [68Ga]Ga-labeled ligands did. Although there are multiple challenges to the use of 66Ga for clinical PET imaging, it can be a valuable research tool for ligand screening and preclinical imaging beyond 24 h.

(68)Ge/ (68)Ga generators: past, present, and future.

In 1964, first (68)Ge/(68)Ga radionuclide generators were described. Although the generator design was by far not adequate to our today's level of chemical, radiopharmaceutical and medical expectations, it perfectly met the needs of molecular imaging of this period. (68)Ga-EDTA as directly eluted from the generators entered the field of functional diagnosis, in particular for brain imaging. A new type of generators became commercially available in the first years of the 21st century. Generator eluates based on hydrochloric acid provided "cationic" (68)Ga instead of "inert" (68)Ga-complexes and opened new pathways of Me(III) based radiopharmaceutical chemistry. The impressive success of utilizing (68)Ga- DOTA-octreotides and PET/CT instead of e.g., (111)In-DTPA-octreoscan and SPECT paved the way not only towards clinical acceptance of this particular tracer for imaging neuroendocrine tracers, but to the realisation of the great potential of the (68)Ge/(68)Ga generator for modern nuclear medicine in general. The last decade has seen a (68)Ga rush. Increasing applications of generator based (68)Ga radiopharmaceuticals (for diagnosis alone, but increasingly for treatment planning thanks to the inherent option as expressed by THERANOSTICS), now ask for further developments - towards the optimization of (68)Ge/(68)Ga generators both from chemical and regulatory points of view. Dedicated chelators may be required to broaden the feasibility of (68)Ga labeling of more sensitive targeting vectors and generator chemistry may be adopted to those chelators - or vice versa. This review describes the development and the current status of (68)Ge/(68)Ga radionuclide generators.

(67)Ga and (68)Ga purification studies: preliminary results.

The positron emission tomography technique is very useful for diagnosis of several diseases. (68)Ga is a positron emitter with half-life of 67.7 min. As it is available from (68)Ge/(68)Ga generator systems, it is not necessary to have a nearby cyclotron. However, the eluate from commercial generators contains high levels of metallic impurities, which compete with (68)Ga in biomolecular labeling. Thus, a subsequent purification step is needed after generator elution. Here we present the results of two different methods developed for handmade purification of (68)Ga and (67)Ga for subsequent radiolabeling of biomolecules. Two purification methods were employed. The first one uses a cation exchange resin, and (68)Ga is eluted with a solution of acetone/acid. The second method of purification is performed by column chromatography solvent extraction, with (68)Ga recovery in deionized water. The best result was achieved with cationic resin AG50W-X8 (>400 mesh). However, the resin is not commercially available. The extraction chromatography column based on absorption of diisopropyl ether in XAD-16 is the most promising purification method. Although the levels of (68)Ga recovery and purification were smaller with the cationic resin method, its advantage is the (68)Ga recovery in deionized water.

Overview and perspectives on automation strategies in (68)Ga radiopharmaceutical preparations.

The renaissance of (68)Ga radiopharmacy has led to great advances in automation technology. The availability of a highly efficient, reliable, long-lived (68)Ge/(68)Ga generator system along with a well-established coordination chemistry based on bifunctional chelating agents have been the bases of this development in (68)Ga radiopharmacy. Syntheses of (68)Ga peptides were originally performed by manual or semiautomated systems, but increasing clinical demand, radioprotection, and regulatory issues have driven extensive automation of their production process. Several automated systems, based on different post-processing of the (68)Ga generator eluate, on different engineering, and on fixed tubing or disposable cassette approaches, have been developed and are discussed in this chapter. Since automatic systems for preparation of radiopharmaceuticals should comply with qualification and validation protocols established by regulations such as current Good Manufacturing Practices (cGMP) and local regulations, some regulatory issues and the more relevant qualification protocols are also discussed.

(68)Ga generator integrated system: elution-purification-concentration integration.

A (68)Ge/(68)Ga generator combined with an automated (68)Ga eluate purification-concentration unit [radioisotope generator integrated system (RADIGIS)], specially designed for (68)Ga processing (RADIGIS-(68)Ga), was developed. The high-stability sorbents of a nanocrystalline structure Zr-Ti ceramic matrix were used for immobilizing the (68)Ge, and the (68)Ga was eluted from the sorbent column with 3.5 mL 0.05-0.1 M HCl solution following an optimized (68)Ga-elution schedule. The (68)Ge breakthrough <10(-3)% and no (68)Ge zone spreading/drift found in PET imaging of the (68)Ga generator column prove the excellent performance of the sorbents. (68)Ga eluate was purified on a small column of salt-form ion exchange resin using an aqueous alcohol solution mixture of hydrochloric and ascorbic acids, and halide salts. An alkali solution was used for stripping (68)Ga from the ion exchange resin column to obtain a purified (68)Ga solution, which is conditioned with acidic solution to obtain a final (68)Ga product in either 0.75 mL 0.5 M NaCl solution of pH 3-4 or 0.5 M sodium acetate or citrate solution of pH 5. The (68)Ge content in purified (68)Ga solution was <10(-6)%. An insignificant metallic contamination including (68)Zn found in the (68)Ga solution and its alkalinity-acidity were evaluated with respect to (68)Ga radiolabeling efficacy for DOTATATE and DOTATOC ligands. Quality control protocols were also developed to evaluate the quality of (68)Ga solution.

Early experience with (68)Ga-DOTATATE preparation.

Neuroendocrine tumors (NETs) are a rare form of cancer. NETs frequently express cell membrane-specific peptide receptors, such as somatostatin receptors (SSTRs). Radiolabeled peptides bind to SSTR and provide in vivo histopathological information for diagnostic purposes. (68)Ga-DOTATATE has higher sensitivity for low-grade tumors and greater avidity to well-differentiated NETs than (18)F-FDG, being superior to (111)In-DTPA-octreotide and (18)F-DOPA in evaluation of well-differentiated metastatic NETs. The feasibility of (68)Ga-DOTATATE application in routine clinical practice for PET imaging of NETs was determined in a limited number of known cases (n = 6). (68)Ga-DOTATATE scan could detect all known sites of NETs and in one case previously unknown peritoneal metastasis. Early regulatory consideration is important for routine clinical use.

Measurement of protein synthesis: in vitro comparison of (68)Ga-DOTA-puromycin, [ (3)H]tyrosine, and 2-fluoro-[ (3)H]tyrosine.

AIM: Puromycin has played an important role in our understanding of the eukaryotic ribosome and protein synthesis. It has been known for more than 40 years that this antibiotic is a universal protein synthesis inhibitor that acts as a structural analog of an aminoacyl-transfer RNA (aa-tRNA) in eukaryotic ribosomes. Due to the role of enzymes and their synthesis in situations of need (DNA damage, e.g., after chemo- or radiation therapy), determination of protein synthesis is important for control of antitumor therapy, to enhance long-term survival of tumor patients, and to minimize side-effects of therapy. Multiple attempts to reach this goal have been made through the last decades, mostly using radiolabeled amino acids, with limited or unsatisfactory success. The aim of this study is to estimate the possibility of determining protein synthesis ratios by using (68)Ga-DOTA-puromycin ((68)Ga-DOTA-Pur), [(3)H]tyrosine, and 2-fluoro-[(3)H]tyrosine and to estimate the possibility of different pathways due to the fluorination of tyrosine. METHODS: DOTA-puromycin was synthesized using a puromycin-tethered controlled-pore glass (CPG) support by the usual protocol for automated DNA and RNA synthesis following our design. (68)Ga was obtained from a (68)Ge/(68)Ga generator as described previously by Zhernosekov et al. (J Nucl Med 48:1741-1748, 2007). The purified eluate was used for labeling of DOTA-puromycin at 95°C for 20 min. [(3)H]Tyrosine and 2-fluoro-[(3)H]tyrosine of the highest purity available were purchased from Moravek (Bera, USA) or Amersham Biosciences (Hammersmith, UK). In vitro uptake and protein incorporation as well as in vitro inhibition experiments using cycloheximide to inhibit protein synthesis were carried out for all three substances in DU145 prostate carcinoma cells (ATCC, USA). (68)Ga-DOTA-Pur was additionally used for µPET imaging of Walker carcinomas and AT1 tumors in rats. Dynamic scans were performed for 45 min after IV application (tail vein) of 20-25 MBq (68)Ga-DOTA-Pur. RESULTS: No significant differences in the behavior of [(3)H]tyrosine and 2-fluoro-[(3)H]tyrosine were observed. Uptake of both tyrosine derivatives was decreased by inhibition of protein synthesis, but only to a level of 45-55% of initial uptake, indicating no direct link between tyrosine uptake and protein synthesis. In contrast, (68)Ga-DOTA-Pur uptake was directly linked to ribosomal activity and, therefore, to protein synthesis. (68)Ga-DOTA-Pur µPET imaging in rats revealed high tumor-to-background ratios and clearly defined regions of interest in the investigated tumors. SUMMARY: Whereas the metabolic pathway of (68)Ga-DOTA-Pur is directly connected with the process of protein synthesis and shows high tumor uptake during µPET imaging, neither [(3)H]tyrosine nor 2-fluoro-[(3)H]tyrosine can be considered useful for determination of protein synthesis.

Purification and labeling strategies for (68)Ga from (68)Ge/ (68)Ga generator eluate.

For successful labeling, (68)Ge/(68)Ga generator eluate has to be concentrated (from 10 mL or more to less than 1 mL) and to be purified of metallic impurities, especially Fe(III), and (68)Ge breakthrough. Anionic, cationic and fractional elution methods are well known. We describe two new methods: (1) a combined cationic-anionic purification and (2) an easy-to-use and reliable cationic purification with NaCl solution. Using the first method, (68)Ga from 10 mL generator eluate was collected on a SCX cartridge, then eluted with 1.0 mL 5.5 M HCl directly on an anion exchanger (30 mg AG1X8). After drying with a stream of helium, (68)Ga was eluted with 0.4 mL water into the reaction vial. We provide as an example labeling of BPAMD. Using the second method, (68)Ga from 10 mL generator eluate was collected on a SCX cartridge, then eluted with a hydrochloric solution of sodium chloride (0.5 mL 5 M NaCl, 12.5 µL 5.5 M HCl) into the reaction vial, containing 40 µg DOTATOC and 0.5 mL 1 M ammonium acetate buffer pH 4.5. After heating for 7 min at 90°C, the reaction was finished. Radiochemical purity was higher than 95% without further purification. No (68)Ge breakthrough was found in the final product.

Post-processing via cation exchange cartridges: versatile options.

New (68)Ge/(68)Ga radionuclide generators provide the positron emitter (68)Ga (T½ = 67.7 min) as an easily available and relatively inexpensive source of a PET nuclide for labeling of interesting targeting vectors. However, currently available "ionic" (68)Ge/(68)Ga radionuclide generators are not necessarily optimized for the routine synthesis of (68)Ga-labeled radiopharmaceuticals in a clinical environment. Post-processing of (68)Ge/(68)Ga generators using cation exchange resins provides chemically and radiochemically pure (68)Ga with 97±2% within less than 4 min, with (68)Ge almost completely removed, and ready for online labeling. This simple, fast, and efficient technology can be extended for new applications. The options are (a) to transfer (68)Ga from the cation exchange resin onto an anion exchange resin, to remove acetone, and to further purify the (68)Ga, (b) to obtain (68)Ga in pure non-aqueous solution via (68)Ga(acac)(3) as a synthon for syntheses in organic solvents, and (c) to create an option toward instantaneous determination of (68)Ge breakthrough, what may be required prior to the release of (68)Ga radiopharmaceutical preparations.

Feasibility and availability of 68Ga-labelled peptides.

(68)Ga has attracted tremendous interest as a radionuclide for PET based on its suitable half-life of 68 min, high positron emission yield and ready availability from (68)Ge/(68)Ga generators, making it independent of cyclotron production. (68)Ga-labelled DOTA-conjugated somatostatin analogues, including DOTA-TOC, DOTA-TATE and DOTA-NOC, have driven the development of technologies to provide such radiopharmaceuticals for clinical applications mainly in the diagnosis of somatostatin receptor-expressing tumours. We summarize the issues determining the feasibility and availability of (68)Ga-labelled peptides, including generator technology, (68)Ga generator eluate postprocessing methods, radiolabelling, automation and peptide developments, and also quality assurance and regulatory aspects. (68)Ge/(68)Ga generators based on SnO(2), TiO(2) or organic matrices are today routinely supplied to nuclear medicine departments, and a variety of automated systems for postprocessing and radiolabelling have been developed. New developments include improved chelators for (68)Ga that could open new ways to utilize this technology. Challenges and limitations in the on-site preparation and use of (68)Ga-labelled peptides outside the marketing authorization track are also discussed.

Taking cyclotron 68Ga production to the next level: Expeditious solid target production of 68Ga for preparation of radiotracers.

INTRODUCTION: Gallium-68 is an important radionuclide for positron emission tomography (PET) with steadily increasing applications of 68Ga-based radiopharmaceuticals for clinical use. Current 68Ga sources are primarily 68Ge/68Ga-generators, along with successful attempts of 68Ga production using a cyclotron. This study evaluated cyclotron 68Ga production and automated separation using expeditiously manufactured solid targets, demonstrates an order of magnitude improvement in yield compared to 68Ge/68Ga generators, and presents a convenient alternative to existing cyclotron production processes. A comparison of radiolabeling and preclinical PET imaging was performed with both cyclotron and generator produced 68Ga. METHODS: 100 mg enriched 68Zn (99.3% 68Zn, 0.48% 67Zn, 0.1% 66Zn) pellets pressed on silver discs were bombarded for 20-75 min using 12.5 MeV proton beam energies and 10-30 µA currents. 68Ga was separated using an automated TRASIS AllinOne synthesizer employing AG 50W-X8 and UTEVA resins. Post-separation recovery of the 68Zn by electrolysis yielded 76.7 ± 4.3%. Radionuclidic purity of cyclotron-produced 68Ga was investigated with gamma spectroscopy using a HPGe-detector. Radiolabeling was investigated using the macrocyclic chelator DOTA and the bombesin-derived peptide NOTA-BBN2. PET imaging was performed using [68Ga]Ga-NOTA-BBN2 in a PC3 xenograft model. RESULTS: 600 µA·min fresh and recycled quadruplet 68Zn target irradiations (n = 8) at 12.5 MeV and 30 µA yielded 13.9 ± 1.0 GBq 68Ga; 2200 µA·min irradiations (n = 3) yielded 37.5 ± 1.9 GBq 68Ga. HPGe analysis showed EOB 0.0074% and 0.0084% of total activity of 66Ga and 67Ga, respectively. Metal impurities were 0.06 ± 0.03 µg/GBq Zn, 0.13 ± 0.007 µg/GBq Fe, and 0.02 ± 0.01 µg/GBq Al for cyclotron 68Ga. Cyclotron and 68Ge/68Ga generator 68Ga respective DOTA and NOTA-BBN2 labeling incorporations were 99.4 ± 0.0% and 99.3 ± 0.2%, and 90.4 ± 1.5% and 93.0 ± 3.6% determined by radio-thin layer chromatography (radio-TLC). Preclinical PET imaging comparison between generator and cyclotron produced 68Ga showed identical radiotracer tumor uptake and biodistribution profiles in PC3 tumor bearing mice. CONCLUSIONS: Cyclotron 68Ga production provides highly scalable production with equivalent or superior quality 68Ga to a 68Ge/68Ga generator, while providing identical biodistribution and tumor uptake profiles. Our described targetry is simpler and more cost-effective than existing liquid and solid targetry, enabling a turnkey production system for multi-facility distribution of cyclotron produced 68Ga. The manufacturing simplicity described has potential applications for producing other radiometals such as 44Sc. ADVANCES IN KNOWLEDGE AND IMPLICATIONS FOR PATIENT CARE: Our cost-effective method of solid target 68Ga production can enhance 68Ga production capabilities to meet the high demand for 68Ga-radiopharmaceuticals for research and clinical use.

Rapid and automated production of [68Ga]gallium chloride and [68Ga]Ga-DOTA-TATE on a medical cyclotron.

INTRODUCTION: The demand for Gallium-68 (68Ga) for labelling PET radiopharmaceuticals has increased over the past few years. 68Ga is obtained through the decayed parent radionuclide 68Ge using commercial 68Ge/68Ga generators. The principal limitation of commercial 68Ge/68Ga generators is that only a limited and finite quantity of 68Ga (<1.85 GBq at start of synthesis) may be accessed. The focus of this study was to investigate the use of a low energy medical cyclotron for the production of greater quantities of 68Ga and to develop an automated and rapid procedure for processing the product. METHODS: Enriched ZnCl2 was electrodeposited on a platinum backing using a NH4Cl (pH 2-4) buffer. The Zn target was irradiated with GE PETtrace 880 at 35 µA and 14.5 and 12.0 MeV beam energy. The irradiated Zn target was purified using octanol resin on an automated system. RESULTS: Following the described procedure, 68Ga was obtained in 6.30 ±â€¯0.42 GBq after 8.5 min bombardment and with low radionuclidic impurities (66Ga (<0.005%) and 67Ga (<0.09%)). Purification on a single octanol resin gave 82% recovery with resulting [68Ga]GaCl3 obtained in 3.5 mL of 0.2 M HCl. [68Ga]GaCl3 production from irradiation to final product was <45 min. To highlight the utility of the automated procedure, [68Ga]Ga-DOTA-TATE labelling was incorporated to give 1.56 GBq at EOS of the labelled peptide with RCY of >70%. CONCLUSIONS: A straightforward procedure for producing 68Ga on a low energy medical cyclotron was described. Current efforts are focus on high activity production and radiolabelling using solid target produced 68Ga.

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.

Production of curie quantities of 68Ga with a medical cyclotron via the 68Zn(p,n)68Ga reaction.

PET imaging with 68Ga-labeled tracers has seen a dramatic increase over the past five years primarily due to the increased accessibility of 68Ge/68Ga generators, the availability of tracers with superb targeting properties for labeling, straightforward labeling procedures and the approval of these tracers by regulatory entities. Available 68Ge/68Ga generators nominally deliver up to 1.85 GBq (50mCi) when fresh limiting production and distribution of 68Ga-labeled tracers to a few daily doses per generator. The focus of this study was to provide a simple and efficient method for 68Ga production in clinically relevant quantities using a low energy medical cyclotron with a solid target.

Processing of generator-produced 68Ga for medical application.

UNLABELLED: The (68)Ge/(68)Ga generator provides an excellent source of positron-emitting (68)Ga. However, newly available "ionic" (68)Ge/(68)Ga radionuclide generators are not necessarily optimized for the synthesis of (68)Ga-labeled radiopharmaceuticals. The eluates have rather large volumes, a high concentration of H(+) (pH of 1), a breakthrough of (68)Ge, increasing with time or frequency of use, and impurities such as stable Zn(II) generated by the decay of (68)Ga, Ti(IV) as a constituent of the column material, and Fe(III) as a general impurity. METHODS: We have developed an efficient route for the processing of generator-derived (68)Ga eluates, including the labeling and purification of biomolecules. Preconcentration and purification of the initial generator eluate are performed using a miniaturized column with organic cation-exchanger resin and hydrochloric acid/acetone eluent. The purified fraction was used for the labeling of nanomolar amounts of octreotide derivatives either in pure aqueous solution or in buffers. RESULTS: Using the generator post-eluate processing system, >97% of the initially eluated (68)Ga activity was obtained within 4 min as a 0.4-mL volume of a hydrochloric acid/acetone fraction. The initial amount of (68)Ge(IV) was decreased by a factor of 10(4), whereas initial amounts of Zn(II), Ti(IV), and Fe(III) were reduced by factors of 10(5), 10(2), and 10, respectively. The processed (68)Ga fraction was directly transferred to solutions containing labeling precursors-for example, DOTA-dPhe(1)-Tyr(3)-octreotide (DOTATOC) (DOTA = 1,4,7,10-tetraazacyclododecane-N,N',N'',N'''-tetraacetic acid). Labeling yields of >95% were achieved within 10 min. Overall yields reached 70% at 20 min after generator elution relative to the eluted (68)Ga activity, not corrected for decay. Specific activities of (68)Ga-DOTATOC were 50 MBq/nmol using a standard protocol, reaching 450 MBq/nmol under optimized conditions. CONCLUSION: Processing on a cation-exchanger in hydrochloric acid/acetone media represents an efficient strategy for the concentration and purification of generator-derived (68)Ga(III) eluates. The developed scheme guarantees high yields and safe preparation of injectable (68)Ga-labeled radiopharmaceuticals for routine application and is easy to automate. Thus, it is being successfully used in clinical environments and might contribute to a new direction for clinical PET, which could benefit significantly from the easy and safe availability of the radionuclide generator-derived metallic positron-emitter (68)Ga.

Separation of no-carrier-added 66,67Ga produced in heavy ion-induced cobalt target using alginate biopolymers.

Heavy ion activation of natural cobalt foil with 84MeV (12)C results in the formation of no-carrier-added (nca) (66,67)As radionuclides, along with their corresponding decay products, (66,67)Ge and (66,67)Ga, in the matrix. Because arsenic and germanium radionuclides are short-lived, after a cooling period of 10h only nca gallium radionuclides remain in the matrix. We attempted to separate the nca gallium radionuclides from the target matrix cobalt by biopolymeric calcium alginate (CA) and Fe-doped calcium alginate (Fe-CA) beads. A complete separation has been achieved by adsorbing (66,67)Ga and a lesser amount of bulk cobalt at pH 3 on Fe-CA beads, followed by desorbing cobalt from the beads with 0.4M NaNO(2).

68Ga 'vacuum elution approach' for direct radiolabelling of DOTA-conjugated and NODAGA-conjugated peptides.

BACKGROUND/OBJECTIVES: The Ge/Ga generator is of increasing interest for clinical PET. The arrival on the market of the pharmaceutical-grade generator, which provides an eluate with chemical and radiochemical purities in conformity with the European Pharmacopeia specifications, makes the direct labelling of vectors possible. The kit formulation strategies using single vial productions can improve the access of hospitals and imaging centres that are not equipped with costly automated synthesis modules to the Ga-radiopharmaceutical production. The manual radiosynthesis of Ga requires handling of a relatively high amount of radioactivity, resulting in a high radiation dose to the hand. Moreover, the elution of the Ga/Ge generator with 5 ml of HCl as recommended by the manufacturer leads to a low Ga concentration, which can decrease the efficiency of the labelling procedure. The aim of our approach is to circumvent these disadvantages and to offer an alternative to the hand elution and labelling for a routine production of Ga-radiopharmaceuticals. METHODS: A mixture of buffer and peptide was first transferred to an evacuated collection vial. Fixed volume of HCl was adapted to the inlet line of the generator. The elution was then performed by the action of vacuum and the labeling occurs at RT or 95°C. RESULTS AND CONCLUSION: The 'vacuum elution approach' developed in this work enables the elution of 95% of the available generator activity with 2.5 ml of eluent, the direct labelling of DOTA-conjugated and NODAGA-conjugated peptides with high radiochemical (>97% for all cases) and radionuclidic (100%) purities without exposure of the hand to radiation during the preparation steps.

Preparation of 68Ga-labelled DOTA-peptides using a manual labelling approach for small-animal PET imaging.

(68)Ga-DOTA-peptides are a promising PET radiotracers used in the detection of different tumours types due to their ability for binding specifically receptors overexpressed in these. Furthermore, (68)Ga can be produced by a (68)Ge/(68)Ga generator on site which is a very good alternative to cyclotron-based PET isotopes. Here, we describe a manual labelling approach for the synthesis of (68)Ga-labelled DOTA-peptides based on concentration and purification of the commercial (68)Ga/(68)Ga generator eluate using an anion exchange-cartridge. (68)Ga-DOTA-TATE was used to image a pheochromocytoma xenograft mouse model by a microPET/CT scanner. The method described provides satisfactory results, allowing the subsequent (68)Ga use to label DOTA-peptides. The simplicity of the method along with its implementation reduced cost, makes it useful in preclinical PET studies.

Evaluation of excitation functions of the (68,67,66)Zn(p,xn)(68,67,66)Ga and 67Zn(p,α)64Cu reactions: validation of evaluated data through comparison with experimental excitation functions of the (nat)Zn(p,x)(66,67)Ga and (nat)Zn(p,x)64Cu processes.

Experimentally available cross section data for formation of the radionuclides (68)Ga, (67)Ga, (66)Ga and (64)Cu in proton induced reactions on enriched (68)Zn, (67)Zn and (66)Zn were evaluated by comparison with the excitation functions calculated by the nuclear model codes, EMPIRE and TALYS, followed by statistical fitting of the selected data. The recommended cross sections were used to obtain the integral yields. The validation of the recommended excitation functions was also attempted by normalization to (nat)Zn and comparison with the experimental data for the (nat)Zn(p,x)(67)Ga, (nat)Zn(p,x)(66)Ga and (nat)Zn(p,x)(64)Cu processes.

Production and purification of gallium-66 for preparation of tumor-targeting radiopharmaceuticals.

Gallium-66 (T(1/2) = 9.49 h) is an intermediate-lived radionuclide that has potential for positron emission tomography (PET) imaging of biological processes with intermediate to slow target tissue uptake. We have produced (66)Ga by the (66)Zn(p,n) (66)Ga nuclear reaction using a small biomedical cyclotron and have investigated methods for purifying (66)Ga that could be applied to the development of an automated processing system. Measured yields of (66)Ga were very high with a production yield of nearly 14 mCi/microA-h at 14.5 MeV bombardment energy, a value in excellent agreement with theoretical predictions based on literature cross sections for the (66)Zn(p,n) (66)Ga reaction. Gallium-66 has been purified from irradiated zinc targets two ways, by cation-exchange chromatography and diisopropyl ether extraction. The concentrations of stable contaminants in (66)Ga following the two processing methods were determined, and it was found that iron and zinc were present at levels up to an order of magnitude higher after cation-exchange chromatography. The bioconjugates DOTA-Tyr(3)-octreotide and DOTA-biotin were labeled with (66)Ga purified by both methods. Following purification of (66)Ga by solvent extraction, radiochemical yields in excess of 85% were obtained for both compounds, in contrast to much lower labeling yields (less than 20%) obtained after the cation-exchange separation. Higher concentrations of stable contaminants likely contributed to the poor radiochemical yields for labeling DOTA-Tyr(3)-octreotide and DOTA-biotin with cation-exchanged (66)Ga. The lower purity and radiolabeling yields obtained using cation-exchange do not warrant the development of an automated processing system based on this method. Therefore, work is in progress to automate the diisopropyl ether extraction method for routine processing of (66)Ga.