Improved column-based radiochemical processing of the generator produced 68Ga

Chemical radioanalysis of production of positron-emitting radioisotope Gallium-68 via (p,n) and (p,2n) reactions using compact cyclotron for tomography applications

In this study, the proton-induced reactions of 68Zn and 69Ga aimed at generating 68Ga were simulated and modeled using Talys code and neural network software. In the first step, both targets were simulated under different proton energies and at different bombardments times to generate a total of six thousand data. Then, the obtained data from the Talys, including the various cross-sections, contaminations, the main product i.e. 68Ga, and other options were completely saved in the output file. Afterwards, the inputs of the neural network were selected from the output of the Talys by analyzing and considering most of the key features. A total of four inputs, two of which are different energies related to the reaction, the other is the process sequence and the fourth input is the bombardment time, were recognized as suitable inputs and the model was trained differently depending on the type of target. The selected model was a feed-forward neural network with 5 nodes in a middle layer, which was able to estimate the output of Talys code by changing the input parameters with extremely high accuracy. Two different models including the main model for estimating the output of the main sample (product) and the sub-model for estimating process pollution or impurity were trained, and then the trained model was tested on the deduced process data. The implementation results fully demonstrated the high accuracy of the method. The neural network model is much easier to implement than the Talys code, and its execution speed is very high. In addition, it can be used appropriately as a system alternative for optimization and different structures in medical and biological engineering.

Behaviour of DGA and Ln resin with alpha radiation dose

In this work the separation efficiency of the DGA and Ln extraction chromatographic resins has been investigated as a function of absorbed dose induced by alpha radiation. It was found that the resins show good stability towards alpha radiolysis, both maintaining high weight distribution ratios (and resin capacity factors) with the absorbed dose, calculated as if the complete alpha energy would be absorbed only in the resin material. However, the results obtained for Ln resin indicates that the method used in this work (extractive distribution ratio) to investigate alpha radiolytic behaviour is not appropriate. The reason is likely the strong acid dependency of this particular extraction system. The behaviour of the DGA resin towards alpha radiolysis was compared to alpha radiolysis in ordinary liquid-liquid extraction of an organic solvent based on the same extractant, TODGA, dissolved in n-dodecan. It was found that the alpha radiolysis rate of TODGA is about 5 times higher in liquid-liquid extraction where the complete energy of the alpha particle is deposited within the solvent, compared to the DGA resin. This indicates that in the heterogeneous DGA resin system, only 20% of the alpha energy is actually deposited to the organic solvent layered onto the particles of the DGA resin.

Radiolabeling of DOTA-like conjugated peptides with generator-produced (68)Ga and using NaCl-based cationic elution method

Gallium-68 (⁶⁸Ga) is a generator-produced radionuclide with a short half-life (t_½ = 68 min) that is particularly well suited for molecular imaging by positron emission tomography (PET). Methods have been developed to synthesize ⁶⁸Ga-labeled imaging agents possessing certain drawbacks, such as longer synthesis time because of a required final purification step, the use of organic solvents or concentrated hydrochloric acid (HCl). In our manuscript, we provide a detailed protocol for the use of an advantageous sodium chloride (NaCl)-based method for radiolabeling of chelator-modified peptides for molecular imaging. By working in a lead-shielded hot-cell system, ⁶⁸Ga³⁺ of the generator eluate is trapped on a cation exchanger cartridge (100 mg, ∼8 mm long and 5 mm diameter) and then eluted with acidified 5 M NaCl solution directly into a sodium acetate-buffered solution containing a DOTA (1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid) or DOTA-like chelator-modified peptide. The main advantages of this procedure are the high efficiency and the absence of organic solvents. It can be applied to a variety of peptides, which are stable in 1 M NaCl solution at a pH value of 3–4 during reaction. After labeling, neutralization, sterile filtration and quality control (instant thin-layer chromatography (iTLC), HPLC and pH), the radiopharmaceutical can be directly administered to patients, without determination of organic solvents, which reduces the overall synthesis-to-release time. This procedure has been adapted easily to automated synthesis modules, which leads to a rapid preparation of ⁶⁸Ga radiopharmaceuticals (12–16 min).

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.

68Ga-Based radiopharmaceuticals: production and application relationship

The contribution of ⁶⁸Ga to the promotion and expansion of clinical research and routine positron emission tomography (PET) for earlier better diagnostics and individualized medicine is considerable. The potential applications of ⁶⁸Ga-comprising imaging agents include targeted, pre-targeted and non-targeted imaging. This review discusses the key aspects of the production of ⁶⁸Ga and ⁶⁸Ga-based radiopharmaceuticals in the light of the impact of regulatory requirements and endpoint pre-clinical and clinical applications.

Cation exchange-based post-processing of (68)Ga-eluate: a comparison of three solvent systems for labelling of DOTATOC, NO2AP(BP) and DATA(m.)

Interest in (68)Ga has led to a number of innovations for its provision suitable for clinical application. Several post-processing methods are available to reduce eluate volume and remove metal trace impurities. In this work three cation exchange resin based post-processing methods (acetone, ethanol and NaCl) have been compared, using three model precursors (DOTATOC, NO2AP(BP) and DATA(m)), in terms of labelling yield and reproducibility. The acetone and ethanol based methods provided greater reproducibility and yields that makes subsequent purification unnecessary.

[(68)Ga]FSC-(RGD)3 a trimeric RGD peptide for imaging αvβ3 integrin expression based on a novel siderophore derived chelating scaffold-synthesis and evaluation

Over the last years Gallium-68 ((68)Ga) has received tremendous attention for labeling of radiopharmaceuticals for positron emission tomography (PET). (68)Ga labeling of biomolecules is currently based on bifunctional chelators containing aminocarboxylates (mainly DOTA and NOTA). We have recently shown that cyclic peptide siderophores have very good complexing properties for (68)Ga resulting in high specific activities and excellent metabolic stabilities, in particular triacetylfusarinine-C (TAFC). We postulated, that, starting from its deacetylated form (Fusarinine-C (FSC)) trimeric bioconjugates are directly accessible to develop novel targeting peptide based (68)Ga labeled radiopharmaceuticals. As proof of principle we report on the synthesis and (68)Ga-radiolabeling of a trimeric FSC-RGD conjugate, [(68)Ga]FSC-(RGD)3, targeting αvβ3 integrin, which is highly expressed during tumor-induced angiogenesis. Synthesis of the RGD peptide was carried out applying solid phase peptide synthesis (SPPS), followed by the coupling to the siderophore [Fe]FSC via in situ activation using HATU/HOAt and DIPEA. Subsequent demetalation allowed radiolabeling of FSC-(RGD)3 with (68)Ga. The radiolabeling procedure was optimized regarding peptide amount, reaction time, temperature as well buffer systems. For in vitro evaluation partition coefficient, protein binding, serum stability, αvβ3 integrin binding affinity, and tumor cell uptake were determined. For in vitro tests as well as for the biodistribution studies αvβ3 positive human melanoma M21 and αvβ3 negative M21-L cells were used. [(68)Ga]FSC-(RGD)3 was prepared with high radiochemical yield (>98%). Distribution coefficient was -3.6 revealing a hydrophilic character, and an IC50 value of 1.8±0.6 nM was determined indicating a high binding affinity for αvβ3 integrin. [(68)Ga]FSC-(RGD)3 was stable in PBS (pH7.4), FeCl3- and DTPA-solution as well as in fresh human serum at 37°C for 2hours. Biodistribution assay confirmed the receptor specific uptake found in vitro. Uptake in the αvβ3 positive tumor was 4.3% ID/g 60min p.i. which was 3-fold higher than the monomeric [(68)Ga]NODAGA-RGD. Tumor to blood ratio of approx. 8 and tumor to muscle ratio of approx. 7 were observed. [(68)Ga]FSC-(RGD)3 serves as an example for the feasibility of a novel class of bifunctional chelators based on cyclic peptide siderophores and shows excellent targeting properties for αvβ3 integrin in vivo for imaging tumor-induced neovascularization.

Characterization of SnO2-based (68)Ge/ (68)Ga generators and (68)Ga-DOTATATE preparations: radionuclide purity, radiochemical yield and long-term constancy

Background

With the increasing utilization of ⁶⁸Ge-⁶⁸Ga radionuclide generators, ⁶⁸Ga labelled peptides like DOTATATE are receiving more attention in nuclear medicine. On the one hand, the long half-life of the parent nuclide ⁶⁸Ge is an enormous advantage for routine applications, but the question of the long-term stability of the ⁶⁸Ge breakthrough arises, which up to now has scarcely been investigated.

Method

A sum of 123 eluates from four different ⁶⁸Ge-⁶⁸Ga generators (iThemba Labs, Faure, South Africa) and 115 samples of the prepared radiopharmaceutical ⁶⁸Ga-DOTATATE were measured first with a dose calibrator and again after decay of the eluted ⁶⁸Ga via gamma-ray spectrometry. A complete decay curve was recorded for one sample eluate. A further three eluates were eluted in ten fractions of 0.5 ml in order to obtain detailed information concerning the distribution of the two nuclides within the eluates. The influences of factors such as the amount of DOTATATE, addition of Fe³⁺ salts and replacement of HEPES buffer with sodium acetate on the radiochemical synthesis were also tested.

Results

The content of long-lived ⁶⁸Ge breakthrough increases over the entire period of use to more than 100 ppm. The labelling process with the chelator DOTA removes ⁶⁸Ge efficiently. The maximum activity found in the residues of the radiopharmaceuticals investigated in this study was below 10 Bq in nearly all cases. In many cases (12% of the labelled substance), the long-lived parent nuclide could not be identified at all. The labelling process is still viable for reduced amounts of the chelator and with acetate buffer.

Conclusion

Effective doses received by the patient from ⁶⁸Ge in the injected radiopharmaceutical ⁶⁸Ga-DOTATATE are lower than 0.1 μSv and are therefore practically negligible, especially when compared with the contribution of the PET radiopharmaceutical itself. Gamma-ray spectrometry as recommended by the European Pharmacopeia is suitable for quantification of radionuclidic impurities.

Electronic supplementary material

The online version of this article (doi:10.1186/s13550-014-0036-4) contains supplementary material, which is available to authorized users.

68Ga-DOTA and analogs: Current status and future perspectives

The construction of the ⁶⁸Ge/⁶⁸Ga generator has increased application of radiopharmaceuticals labeled with this isotope in medicine. ⁶⁸Ga-PET is widely employed in the management of neuroendocrine tumors but favorable chemistry with tri- and tetraaza-ring molecules has opened wide range of ⁶⁸Ga application in other fields of PET imaging. This review covers the radiopharmaceuticals labeled with gallium in molecular imaging and shows perspectives on the use of gallium-68 as a substitute for technetium-99, fluorine-18 and carbon-11 in some applications.

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.

Long-term evaluation of 'BARC 68Ge/68Ga generator' based on the nanoceria-polyacrylonitrile composite sorbent

This article describes the long-term evaluation of a nanoceria-polyacrylonitrile (CeO2-PAN) composite sorbent-based (68)Ge/(68)Ga generator reported. This generator used the new CeO2-PAN composite sorbent for preparation of the (68)Ge/(68)Ga generator. Since this sorbent has not been previously evaluated, a thorough long-term evaluation of the performance of the generator is necessary to ensure its applicability for clinical practice. The performance of the generator was evaluated in terms of (68)Ga yield, (68)Ge breakthrough, radioactive concentration of the (68)Ga solution, and suitability of the (68)Ga for the preparation of (68)Ga-labeled tracers. The (68)Ge/(68)Ga generator was able to provide a (68)Ga activity with consistent yields (>70%) and having acceptable radionuclidic (<10(-4)% of (68)Ge breakthrough), radiochemical, and chemical purities for an extended period of time. The eluted (68)GaCl3 is useful for the majority of the (68)Ga complexation chemistry.

(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.

68Ge/68Ga Generators and 68Ga Radiopharmaceutical Chemistry on Their Way into a New Century

68Ga faces a renaissance initiated by the development of new 68Ge/68Ga radionuclide generators, sophisticated 68Ga radiopharmaceuticals, preclinical research and state-of-the-art clincial diagnoses via positron emission tomography/computed tomography (PET/CT). A new type of 68Ge/68Ga generator became commercially available in the first years of the 21st century, with eluates based on hydrochloric acid. These generators provided ‘cationic’ 68Ga instead of ‘inert’ 68Gacomplexes, and opened new pathways of MeIII radiopharmaceutical chemistry. The last decade has seen a 68Ga rush. Increasing interest in generator-based 68Ga radiopharmaceuticals in diagnostic applications has been accompanied by its potential use in the context of diease treatment planning, made possible by the inherent option expressed by theranostics. However, widespread acceptance and clinical application requires optimization of 68Ge/68Ga generators both from chemical and regulatory perspectives.

How to cite this article

Rösch F. 68Ge/68Ga Generators and 68Ga Radiopharmaceutical Chemistry on Their Way into a New Century. J Postgrad Med Edu Res 2013;47(1):18-25.

Long-term evaluation of TiO2-based 68Ge/68Ga generators and optimized automation of [68Ga]DOTATOC radiosynthesis

Interest in using (68)Ga is rapidly increasing for clinical PET applications due to its favorable imaging characteristics and increased accessibility. The focus of this study was to provide our long-term evaluations of the two TiO(2)-based (68)Ge/(68)Ga generators and develop an optimized automation strategy to synthesize [(68)Ga]DOTATOC by using HEPES as a buffer system. This data will be useful in standardizing the evaluation of (68)Ge/(68)Ga generators and automation strategies to comply with regulatory issues for clinical use.