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Journal articles on the topic "68Ga generator"
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Rösch, Frank. "68Ge/68Ga Generators and 68Ga Radiopharmaceutical Chemistry on Their Way into a New Century." Journal of Postgraduate Medicine, Education and Research 47, no. 1 (2013): 18–25. http://dx.doi.org/10.5005/jp-journals-10028-1052.
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ABSTRACT 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.
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Sriprapa, Tossaporn, Thanete Doungta, Nopparath Sakulsamart, et al. "Evaluation of the Efficacy and Safety of the ITM 68Ge/68Ga Generator After its Recommended Shelf-life." Siriraj Medical Journal 75, no. 10 (2023): 752–58. http://dx.doi.org/10.33192/smj.v75i10.264289.
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Objective: 68Ga can be routinely produced by a 68Ge/68Ga generator without the need for a cyclotron. It is recommended to replace the 68Ge/68Ga generator after 250 elutions or 12 months of shelf-life whichever endpoint is reached first. However, a 68Ge/68Ga generator that has gone past its recommended lifespan can still be further used as a 68Ga source for 68Ga-labeled radiopharmaceuticals for use in animal experiments. To ensure the quality of 68Ga eluates, we aimed to evaluate the efficacy and safety of the ITM (Isotope Technologies München) 68Ge/68Ga generator in our institute after its recommended shelf-life. Materials and Methods: A 21-month-old ITM 68Ge/68Ga generator was eluted using 4.0 ml of 0.05 M HCl. The 68Ga elution yields were calculated, and 68Ge breakthrough was measured at least 48 h after elution in an aliquot amount using a multichannel analyzer (MCA) with a high-purity germanium probe. Metal impurities in the 68Ga eluates were analyzed by ICP-MS. Results: The elution yield of 68Ga was 35.2 ± 8.1%; n = 5 (decay corrected). 68Ge breakthrough from the ITM 68Ge/68Ga generator was below the detectable level. The average amounts of the metallic ions 57Fe, 66Zn, 203Pb, 60Ni, and 63Cu were 18.60, 9.86, 2.42, 0.52, and 0.47 µg/GBq, respectively. Conclusion: The ITM 68Ge/68Ga generator demonstrated consistent and reliable 68Ga elution profiles with an absence of either 68Ge breakthrough or other metal contaminants in the eluent samples as verified by the manufacturer. The use of the ITM 68Ge/68Ga generator could be extended past its recommended shelf-life to prepare 68Ga radiopharmaceuticals that are considered safe and suitable for use in animal experimentation and other applications.
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Lee, Jun-Young, Pyeong-Seok Choi, Seung-Dae Yang, and Jeong-Hoon Park. "TiO2 Decorated Low-Molecular Chitosan a Microsized Adsorbent for a 68Ge/68Ga Generator System." Molecules 26, no. 11 (2021): 3185. http://dx.doi.org/10.3390/molecules26113185.
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We report column material for a 68Ge/68Ga generator with acid resistance and excellent adsorption and desorption capacity of 68Ge and 68Ga, respectively. Despite being a core element of the 68Ge/68Ga generator system, research on this has been insufficient. Therefore, we synthesized a low molecular chitosan-based TiO2 (LC-TiO2) adsorbent via a physical trapping method as a durable 68Ge/68Ga generator column material. The adsorption/desorption studies exhibited a higher separation factor of 68Ge/68Ga in the concentration range of HCl examined (0.01 M to 1.0 M). The prepared LC-TiO2 adsorbent showed acid resistance capabilities with >93% of 68Ga elution yield and 1.6 × 10−4% of 68Ge breakthrough. In particular, the labeling efficiency of DOTA and NOTA, by using the generator eluted 68Ga, was quite encouraging and confirmed to be 99.65 and 99.69%, respectively. Accordingly, the resulting behavior of LC-TiO2 towards 68Ge/68Ga adsorption/desorption capacity and stability with aqueous HCl exhibited a high potential for ion-exchange solid-phase extraction for the 68Ge/68Ga generator column material.
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Baimukhanova, Ayagoz, Elena Chakrova, Dimitr Karaivanov, Jan Kozempel, Frank Roesch, and Dmitriy Filosofov. "Production of the positron-emitting radionuclide 68Ga: the radiochemical scheme of radionuclide generator 68Ge → 68Ga." Chemical Bulletin of Kazakh National University, no. 2 (June 30, 2018): 20–26. http://dx.doi.org/10.15328/cb1003.
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68Ga (T1 / 2 = 68 min) in complexes with peptides is used in positron emission tomography for diagnostics of neuroendocrine tumors. The most promising strategy for 68Ga production is usage of the radionuclide generator 68Ge → 68Ga. In this research, the sorption behavior of Ge(IV) and Ga (III) has been studied. The distribution coefficients (Kd) of Ge(IV) on the anion exchange (Dowex 1×8) and cation exchange (Dowex 50×8) resins in various ethanedioic and hydrochloric acid solutions were determined. For each ion exchange resin, four series of measurements were carried out, in which the concentration of oxalic acid was fixed (0.001 M, 0.003 M, 0.005 M, 0.01 M), and the concentrations of hydrochloric acid ranged from 0 to 3 M. Based on the distribution coefficients, the chemical scheme of the radionuclide generator 68Ge → 68Ga has been developed. The chemical system is based on the anion exchange resin Dowex 1×8 and mixture of 0.005 M C2H2O4 / 0.33 M HCl. Several types of the generators with direct and reverse mode of elution were tested and the optimal scheme was determined. Elution of the generators was performed once a day with 8 ml of 0.005 M C2H2O4 / 0.33 M HCl solution. The 68Ga yield and the 68Ge breakthrough are comparable for all the systems.
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Jaiuea, Phattarayut, Somlak Kongmuang, Kanyapat Lumyong, Thanete Doungta, and Shuichi Shiratori. "Optimization of the Use of the DOTATATE Kit Manufactured by the Thailand Institute of Nuclear Technology Using a SiO2-based 68Ge/68Ga Generator." Siriraj Medical Journal 76, no. 11 (2024): 789–96. http://dx.doi.org/10.33192/smj.v76i11.270157.
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Objective: The presence of somatostatin receptors on neuroendocrine tumours enables 68Ga-DOTATATE to precisely detect lesion localization and staging. Thailand Institute of Nuclear Technology (TINT) recently developed a DOTATATE kit for labelling with Ga-68, which is compatible with a TiO2-based 68Ge/68Ga generator eluted with 0.1 M HCl, but presents a discrepancy with other types of 68Ge/68Ga generators. This research aimed to optimize a radiolabelling method using TINT’s kit with a SiO2-based 68Ge/68Ga generator eluting Ga-68 in 0.05 M HCl. Additionally, a quality control protocol was developed to ensure the formulation’s efficacy and reliability in compliance with the 10th edition of the European Pharmacopoeia. Material and Methods: The SiO2-based 68Ge/68Ga generator was eluted with 2–4 ml of 0.05 M HCl, added into a lyophilized kit, heated in a dried-block heater at 100 ºC for 15 min, cooled down at room temperature, and finally purified using Sep-Pak C18 cartridge. The radiochemical purity was determined by radio thin-layer chromatography and the radioactivity was measured by a gamma well counter. Reproducibility and stability tests were conducted three times. Results: Employing 4 ml of eluted material, comprising the second and fifth millilitres of 68GaCl3, provided a radiochemical purity (RCP) exceeding 95% after purification. Also, 68Ga-DOTATATE remained stable in refrigerator for at least 4 half-lives. Conclusion: TINT’s DOTATATE kit can be successfully labelled with a SiO2-based 68Ge/68Ga generator, providing 68Ga-DOTATATE with an RCP > 95% for at least 4 half-lives when stored in refrigerator after production. This radiolabelling procedure is suitable for routine clinical application.
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Sriprapa, Tossaporn, Thanete Doungta, Napamon Sritongkul, and Malulee Tantawiroon. "Development of the Purification Process of Gallium-68 Eluted from Germanium-68/Gallium-68 Generator." Siriraj Medical Journal 76, no. 2 (2024): 90–96. http://dx.doi.org/10.33192/smj.v76i2.266113.
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Objective: 68Ga has a half-life of 68 minutes, with 89% of its decay is through positron emission. It is available from generator systems and possesses suitable property for labeling radioligands. These aspects make 68Ga a promising tracer for positron emission tomography (PET) imaging. This study aims to develop the purification process of the 68Ga eluates from 68Ge/68Ga generator after its recommended shelf-life and ensuring the quality through the radiolabeling process. Materials and Methods: In this study, we explored the development of a purification method for 68Ga eluted from a68Ge/68Ga generator before radiolabeling was investigated. Cation and anion exchange chromatography techniques were combined to remove trace amounts of competing metal ion impurities. Post-purification, the eluate’s metal contents were analyzed using inductively coupled plasma atomic emission spectroscopy (ICP-AES). Breakthrough of 68Ge was measured using a multi-channel analyzer (MCA) spectrometer with high-purity germanium (HPGe) radiation detectors. Additionally, the radiochemical purity of 68Ga-NOTA-RGD was analyzed by high-performance liquid chromatography (HPLC). Results: Metal impurities including Fe(II), Zn(II) and Al(III) were reduced by 61%, 38% and 44% respectively. The 68Ge breakthrough was approximately ~10–3%. The labeling efficiency with NOTA-RGD, a tracer for angiogenesis imaging, resulted in an average yield of 68Ga-NOTA-RGD (not corrected for decay) of around 50%, with aradiochemical purity by HPLC of approximately 98%–99%. Conclusion: Cation exchange in combination with anion exchange chromatography was thus proven to be an efficient method for purification of the 68Ga eluate from a 68Ge/68Ga generator prior to labeling the 68Ga PET radiotracer.
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Ambe, Shizuko. "68Ge68Ga generator with alpha-ferric oxide support." International Journal of Radiation Applications and Instrumentation. Part A. Applied Radiation and Isotopes 39, no. 1 (1988): 49–51. http://dx.doi.org/10.1016/0883-2889(88)90091-3.
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Schultz, Michael K., Patrick Donahue, Nannette I. Musgrave, et al. "An Increasing Role for 68Ga PET Imaging: A Perspective on the Availability of Parent 68Ge Material for Generator Manufacturing in an Expanding Market." Journal of Postgraduate Medicine, Education and Research 47, no. 1 (2013): 26–30. http://dx.doi.org/10.5005/jp-journals-10028-1053.
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ABSTRACT The use of gallium-68 for molecular imaging is gaining momentum world-wide. While our understanding of 68Ga chemistry, generators, and associated synthesis modules appear to have advanced to a clinically-reliable stage, uncertainty in the supply of radiopharmaceutically-suitable parent is of significant concern. In this work, we examine the current supply of 68Ge in an effort to better understand the potential for expansion of manufacturing to meet an increasing demand for 68Ga. Although specific information on sales and demand of 68Ge is highly business sensitive and thus guarded, our examination finds no shortage in the current supply of 68Ge. On the other hand, increases in the use of 68Ge generators for clinical applications in the United States point to the need for continued support for production at DOE laboratories in the United States to ensure a reliable supply and suggests that new commercial facilities may be needed to meet the increasing demand. How to cite this article Schultz MK, Donahue P, Musgrave NI, Zhernosekov K, Naidoo C, Razbash A, Tworovska I, Dick DW, Watkins GL, Graham MM, Runde W, Clanton JA, Sunderland JJ. An Increasing Role for 68Ga PET Imaging: A Perspective on the Availability of Parent 68Ge Material for Generator Manufacturing in an Expanding Market. J Postgrad Med Edu Res 2013;47(1):26-30.
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Feng, Yixiao, Yang Shao, Ziao Li, Min Luo, Diandou Xu, and Lingling Ma. "Research Progress on Major Medical Radionuclide Generators." Processes 13, no. 2 (2025): 521. https://doi.org/10.3390/pr13020521.
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As the concept of integrated diagnosis and treatment gains increasing prominence, the utilization of radiopharmaceuticals in personalized medicine has garnered unprecedented attention. However, the production of these radiopharmaceuticals continues to encounter numerous technical challenges. It plays an important role in improving the efficiency and convenience of nuclear medicine services and can quickly and conveniently provide the required radioactive isotopes to meet the needs of integrated clinical diagnosis and treatment while reducing dependence on external supplies and improving safety and the economy. At present, commonly used medical radioactive isotope generators include 99Mo/99mTc, 68Ge/68Ga, 90Sr/90Y, 188W/188Re, etc. This article reviews the latest research progress on three main medical radioactive isotope generators of 99Mo/99mTc, 68Ge/68Ga, and 90Sr/90Y. It also evaluates the highly anticipated new 44Ti/44Sc generator and proposes research prospects for current medical radioactive isotope generators, providing exploration directions for the future development of nuclear medicine.
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Gong, Xiang, Jiali Liu, and Sheng Hu. "Bayberry Tannin-modified SiO2 used for 68Ge/68Ga Generator." Academic Journal of Science and Technology 13, no. 3 (2024): 315–18. https://doi.org/10.54097/7wvzwe35.
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A synthetic method of modified SiO₂ grafted with bayberry tannin (SiO₂-BT) was reported. When the prepared SiO₂-BT was used for the treatment of the mixed solution of Ge and Ga, it could achieve a 99.99% Ge adsorption performance with hardly Ga adsorb. In addition, this SiO₂-BT also exhibited excellent acid resistance, in 0.1-0.5 M HCl solutions, it maintaining over 99.8% Ge adsorption efficiency. The results of radioactive experiments showed that with 10 μCi ⁶⁸Ge loaded, this SiO₂-BT could achieve an elution efficiency of ⁶⁸Ga of 75% while the breakthrough of ⁶⁸Ge maintained below 5×10-6. Overall, this SiO₂-BT has excellent acid resistance, highly efficient ⁶⁸Ga elution, and the characteristic of long-term low ⁶⁸Ge breakthrough, making it a potential adsorbent for ⁶⁸Ge/⁶⁸Ga generators.
Dissertations / Theses on the topic "68Ga generator"
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Costa, Renata Ferreira. "Desenvolvimento de métodos de purificação do Gálio-67 e Gálio-68 para a marcação de biomolécula." Universidade de São Paulo, 2012. http://www.teses.usp.br/teses/disponiveis/85/85131/tde-29062012-141412/.
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Há mais de 50 anos os geradores de 68Ge/68Ga vêm sendo desenvolvidos, obtendo o 68Ga sem a necessidade da instalação de um cíclotron próximo à radiofarmácia ou ao centro hospitalar que tenha um PET/CT. O 68Ga é um emissor de pósitron com baixa emissão de fóton (β+, 89%, 1077 keV) e meia vida de 67,7 minutos, compatível com a farmacocinética de moléculas de baixo peso molecular, como peptídeos e fragmentos de anticorpos. Além disso, a química do Ga permite a ligação estável com agentes quelantes acoplados com peptídeos, como o DOTA. Todas estas características do 68Ga aliado a tecnologia PET/CT permitiram avanços em imagem molecular, como no diagnóstico de doenças de origem neuroendócrina. Entretanto, o eluato de 68Ga proveniente dos geradores de 68Ge/68Ga comerciais, ainda contém altos níveis de contaminantes, como o 68Ge e outros metais que competem quimicamente com o 68Ga, como o Fe3+ e Zn2+ e, como consequência, há redução do rendimento de marcação com biomoléculas. Quanto menor a quantidade de impurezas no eluato, a competição entre o peptídeo radiomarcado e peptídeo não marcado será menor e a qualidade de imagem será melhor, por isso existe a necessidade de diminuir a quantidade destes metais. Portanto, os objetivos deste trabalho são avaliar os métodos de purificação do 68Ga para a marcação de biomoléculas, com ênfase no estudo das impurezas químicas presentes nos radioisótopos primários, e desenvolver um método de purificação inédito. Diversos métodos de purificação foram estudados. Na purificação em resina catiônica tradicional e comercial, em que o 68Ga é adsorvido em resina catiônica e eluído em uma solução de acetona/ácido, a resina utilizada não é disponível comercialmente. Várias resinas catiônicas foram testadas simulando o processo comercial, e o uso das menores partículas da resina catiônica AG50W-X4 (200-400 mesh) foi a que apresentou os melhores resultados. Um método inovador foi a cromatografia por extração, onde o éter diisopropílico é adsorvido em resina XAD 16 e o 68Ga eluído em água deionizada. Apesar dos resultados de recuperação do 68Ga e a separação entre o 68Ga e o 65Zn terem sido bons, não houve reprodutibilidade na purificação dos metais. O método mais promissor e inédito foi a purificação do 68Ga em resina catiônica em meio básico que apresentou bons resultados, principalmente em relação à redução do Zn (98 ± 2)%, o contaminante químico encontrado em maior abundância no eluato de 68Ga. A redução total de impurezas foi (95 ± 4)%. Os peptídeos DOTATOC/DOTATATO foram marcados com o 68Ga em três diferentes formas: purificado em meio básico, por extração por solventes e sem a purificação prévia, o melhor resultado de rendimento de marcação do 68Ga DOTATATO foi obtido após a purificação do 68Ga em meio básico, comprovando a eficiência do processo.<br>For more than fifty years, the long-lived 68Ge/68Ga generators have been in development, obtaining 68Ga without the need of having in house cyclotron, which is a considerable convenience for PET centers that have no nearby cyclotrons. 68Ga decays 89% by positron emission and low photon emission (1077 keV) and the physical half life of 67.7 minutes is compatible with the pharmacokinetics of low biomolecular weight substances like peptides and antibody fragments. Moreover, its established metallic chemistry allows it to be stably bound to the carrier peptide sequence via a suitable bifunctional chelator, such as DOTA. All these reasons together with the technology of PET/CT allowed advances in molecular imaging, in particular in the diagnosis of neuroendocrine diseases. However, the eluate from the commercial 68Ge/68Ga generators still contains high levels of long lived 68Ge, besides other metallic impurities, which competes with 68Ga with a consequent reduction of the labeling yield of biomolecules, such as Fe3+ and Zn2+. Thus, the lower the amount of impurities in the eluate, the competition between the radiolabeled and unlabeled peptide by the receptor will be smaller and the quality of imaging will be better, a subsequent purification step is needed after the generator elution. The aim of this work is to evaluate different purifications methods of 68Ga to label biomolecules, with emphasis on the study of the chemical impurities contained in the eluate and to develop a new purification method. Several purification methods were studied. Many cationic resin were tested simulating the commercial process. 68Ga is adsorbed in cationic resin, which is not commercial available and eluted in acid/acetone solution. The use of minor particles of cationic resin AG50W-X4 (200-400 mesh) showed the best results. An innovate method was the extraction chromatography, wich is based on the absorption of diisopropyl ether in XAD 16 and 68Ga recovery in deionized water. Although the results regarding to 68Ga recovery and the radiochemical separation between 68Ga and 65Zn were excellent, there was no reproducibility on the purification of metals. The most promising and innovative method was the 68Ga purification performed by cationic resin in basic media, which presented the best results, especially regarding the Zn reduction (98 ± 2)%, the chemical contaminant found in great abundance in 68Ga eluate. The total impurities reduction was (95 ± 4)%. The peptides DOTATOC/DOTATATE were labeled 68Ga in three different forms: purified 68Ga in basic solution, through solvent extraction and no purified 68Ga. The best result was achieved with DOTATATE labeling with purified 68Ga in basic media, proving the purification process efficiency.
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Buwa, Sizwe. "Production and evaluation of a TiO2 based 68Ge/68Ga generator." University of the Western Cape, 2014. http://hdl.handle.net/11394/4335.
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>Magister Scientiae - MSc<br>68Ge/68Ga generators rely on metal oxide, inorganic and organic sorbents in order to prepare radionuclides useful for clinical applications. The requirements for 68Ge/68Ga generators are that the 68Ga obtained from the 68Ge loaded column should be optimally suited for the routine synthesis of 68Ga-labelled radiopharmaceuticals, that the separation of the 68Ga daughter from the 68Ge parent should happen easily, with a high yield of separation, a low specific volume of 68Ga and should not contain trace elements owing to the solubility of the metal oxide sorbent. Beginning with a metal oxide preparation and continuing through recent developments, several approaches for processing generator derived 68Ga have altered the production of 68Ge/68Ga generators. Still, the effects of sorbent modification on the properties of 68Ge/68Ga radionuclide generator systems are not necessarily optimally designed for direct application in a medical context. The objective of this research was to analyze and document characteristics of Titanium Oxide (TiO2) sorbents relevant to processing of a 68Ge/68Ga generator that is able to produce 68Ga eluates that are adequate for clinical requirements. Interest was shown in TiO2 based 68Ge/68Ga generators by a number of overseas companies for tumour imaging using 68Ga-labelled 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA)-conjugated peptides. While a method involving production of the 68Ga radionuclide using TiO2 metal oxide had been published, problems with the production persisted. A method, using TiO2 metal oxide for ion exchange chromatography, was devised in this study to produce the 68Ga radionuclide, with the aim of being adopted for production purposes. The study focuses on the development of a dedicated procedure for the achievement of sufficient 68Ga yield along with low 68Ge breakthrough and low metallic impurities. Literature from 1970 to 2011 was reviewed to assess the radiochemical aspects of the 68Ga production and processing thereof. Various commercially available TiO2 metal oxides were characterized by subjecting the materials to x-ray diffraction (XRD), x-ray fluorescence (XRF) and scanning electron microscopy (SEM) for quantitative and qualitative analysis.
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Velikyan, Irina. "Synthesis, Characterisation and Application of 68Ga-labelled Macromolecules." Doctoral thesis, Uppsala universitet, Kemiska institutionen, 2005. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-5876.
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The positron emitting radionuclide 68Ga (T1/2 = 68 min) might become of practical interest for clinical positron emission tomography (PET). The metallic cation, 68Ga(III), is suitable for complexation with chelators, either naked or conjugated with biological macromolecules. Such labelling procedures require pure and concentrated preparations of 68Ga(III), which cannot be sufficiently fulfilled by the presently available 68Ge/68Ga generator eluate. This thesis presents methods to increase the concentration and purity of 68Ga obtained from a commercial 68Ge/68Ga generator. The use of the preconcentrated and purified 68Ga eluate along with microwave heating allowed quantitative 68Ga-labelling of peptide conjugates within 15 min. The specific radioactivity of the radiolabelled peptides was improved considerably compared to previously applied techniques using non-treated generator eluate and conventional heating. A commercial 68Ge/68Ga generator in combination with the method for preconcentration/purification and microwave heated labelling might result in an automated device for 68Ga-based radiopharmaceutical kit production with quantitative incorporation of 68Ga(III). Macromolecules were labelled with 68Ga(III) either directly or via a chelator. The bifunctional chelator, DOTA, was conjugated in solution to peptides, an antibody and oligonucleotides. The peptides had varied pI values, constitution, and length ranging from 8 to 53 amino acid residues. The oligonucleotides were of various sequences and length with modifications in backbone, sugar moiety and both 3' and 5' ends with a molecular weight up to 9.8 kDa. The bioconjugates were labeled with 68Ga(III), and the resulting tracers were characterised chemically and biologically. The identity of the 68Ga-labelled bioconjugates was verified. The tracers were found to be stable and their biological activity maintained. Specific radioactivity was shown to be an important parameter influencing the feasibility of accurate imaging data quantification. Furthermore, 68Ga-labelled peptide imaging was shown to be a useful tool to study peptide adsorption to microstructures in a chemical analysis device.
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Velikyan, Irina. "Synthesis, Characterisation and Application of 68Ga-labelled Macromolecules." Doctoral thesis, Uppsala : Acta Universitetis Upsaliensis : Univ.-bibl. [distributör], 2005. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-5876.
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Schoeman, Isabel. "Qualification of in-house prepared 68Ga RGD in healthy monkeys for subsequent molecular imaging of αvβ3 integrin expression in patients / Isabel Schoeman". Thesis, 2014. http://hdl.handle.net/10394/13428.
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Introduction: Targeted pharmaceuticals for labelling with radio-isotopes for very specific
imaging (and possibly later for targeted therapy) play a major role in Theranostics which is
currently an important topic in Nuclear Medicine as well as personalised medicine. There
was a need for a very specific lung cancer radiopharmaceutical that would specifically be
uptaken in integrin 3 expression cells to image patients using a Positron Emission
Tomography- Computed Tomography (PET-CT) scanner.
Background and problem statement: Cold kits of c (RGDyK)–SCN-Bz-NOTA were kindly
donated by Seoul National University (SNU) to help meet Steve Biko Hospital’s need for
this type of imaging. These cold kits showed great results internationally in labelling with a
0.1 M 68Ge/68Ga generator (t1/2 of 68Ge and 68Ga are 270.8 days and 67.6 min,
respectively). However the same cold kits failed to show reproducible radiolabeling with the
0.6 M generator manufactured under cGMP conditions at iThemba LABS, Cape Town and
distributed by IDB Holland, the Netherlands.
Materials and methods: There was therefore a need for producing an in-house NOTA-RGD
kit that would enable production of clinical 68Ga-NOTA-RGD in high yields from the IDB
Holland/iThemba LABS generator. Quality control included ITLC in citric acid to observe
labelling efficiency as well as in sodium carbonate to evaluate colloid formation. HPLC was
also performed at iThemba LABS as well as Necsa (South African Nuclear Energy
Corporation). RGD was obtained from Futurechem, Korea. Kit mass integrity was
determined by testing labelling efficiency of 10, 30 and 60 μg of RGD per cold kit. The
RGD was buffered with sodium acetate trihydrate. The original kits were dried in a
desiccator and in later studies only freeze dried. Manual labelling was also tested. The
radiolabelled in-house kit’s ex vivo biodistribution in healthy versus tumour mice were
examined by obtaining xenografts. The normal biodistribution was investigated in three
vervet monkeys by doing PET-CT scans on a Siemens Biograph TP 40 slice scanner.
Results: Cold kit formulation radiolabeling and purification methods were established
successfully and SOPs (standard operating procedures) created. HPLC results showed
highest radiochemical purity in 60 μg cold kit vials. 68Ga-NOTA-RGD showed increased
uptake in tumours of tumour bearing mouse. The cold kit also showed normal distribution
according to literature with fast blood clearance and excretion through kidneys into urine,
therefore making it a suitable radiopharmaceutical for clinical studies.
Conclusion: The in-house prepared cold kit with a 4 month shelf-life was successfully
tested in mice and monkeys.<br>MSc (Pharmaceutics), North-West University, Potchefstroom Campus, 2014
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Loktionova, Natalia [Verfasser]. "Development and evaluation of a 44Ti-44Sc radionuclide generator and labeling of biomolecules with 44Sc and 68Ga for PET imaging / Loktionova, Natalia." 2010. http://d-nb.info/1011213117/34.
Full textBooks on the topic "68Ga generator"
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IAEA. Production of Long Lived Parent Radionuclides for Generators: 68ge, 82sr, 90sr And 188W. International Atomic Energy Agency, 2010.
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Fenyves, Attila, Stefan Perner, and Andreas Riedler. VersVG - Versicherungsvertragsgesetz. Verlag Österreich, 2022. http://dx.doi.org/10.33196/9783704689528.
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Der führende Kommentar zum VersVG Der VersVG-Kommentar prägt seit vielen Jahren Rechtsprechung und Wissenschaft im Versicherungsrecht. Die Herausgeber Attila Fenyves, Stefan Perner und Andreas Riedler führten das Werk im Jahr 2020 in eine neue Generation: Das Grundwerk ist erheblich erweitert worden und umfasst nun drei Mappen. Die Umstellung auf Fußnoten erleichtert die Lesbarkeit und die Handhabung in der Praxis. Sukzessive werden sämtliche Kommentierungen aktualisiert und ausgetauscht. Dies soll 2022 abgeschlossen sein. Das Team des Kommentars wird durch neue Autorinnen und Autoren aus Rechtsprechung, Wissenschaft und Anwaltspraxis verstärkt. Sie alle sorgen für eine wissenschaftlich fundierte und gleichzeitig verständliche Erläuterungen der Bestimmungen des VersVG mit klarem Blick Richtung Praxis. Der Kommentar richtet sich an Versicherungsunternehmen, Versicherungsmakler*innen und -agenturen, Rechtsanwaltskanzleien, Gerichte und Lehrende an den Universitäten. Die 9. Lieferung enthält diese Kommentierungen: - §§ 5b, 5c (Rücktritt) durch Attila Fenyves - § 6 (Obliegenheiten) durch Attila Fenyves - § 7-10 (Dauer und Beendigung) durch Andreas Riedler - §§ 13-15b (Insolvenz, Pfändungsschutz, Inländische Gerichtsbarkeit) durch Thomas Aigner, Petra Leupold und Andreas Riedler - Vorbemerkungen §§ 16-22, §§ 16-22 (Vorvertragliche Anzeigepflichten) durch Stephanie Fischer - Vorbemerkungen §§ 49-68a und §§ 49-56 (Schadensversicherung) durch Johann Höllwerth
Book chapters on the topic "68Ga generator"
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Mueller, Dirk, Ingo Klette, and Richard P. Baum. "Purification and Labeling Strategies for 68Ga from 68Ge/68Ga Generator Eluate." In Recent Results in Cancer Research. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-27994-2_5.
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Le, Van So. "68Ga Generator Integrated System: Elution–Purification–Concentration Integration." In Recent Results in Cancer Research. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-27994-2_4.
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Rösch, F. "68Ge/68Ga Generators: Past, Present, and Future." In Recent Results in Cancer Research. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-27994-2_1.
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Meisenheimer, Michael, Yury Saenko, and Elisabeth Eppard. "Gallium-68: Radiolabeling of Radiopharmaceuticals for PET Imaging - A Lot to Consider." In Medical Isotopes. IntechOpen, 2021. http://dx.doi.org/10.5772/intechopen.90615.
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Gallium-68 was applied for positron emission tomography (PET) imaging already in the early beginnings of PET imaging. Today, with the introduction of PSMA-targeting tracers (e.g. PSMA-11, PSMA-617, and PSMA-I&T), the number of clinical applications of 68Ga-radiopharmaceuticals for diagnostic imaging has grown considerably. This development was initiated and supported already in the mid-2000s by the commercial availability of 68Ge/68Ga generators designed for clinical usage. This progression was accompanied by the development of several purification methods to generator eluate as well as sophisticated 68Ga-radiopharmaceuticals. Due to the 68Ga-rush, the need for implementation of gallium-68 (depending on production route) and its certain tracers into the pharmacopeia increased. Based on the specifications given by the pharmacopeia, interest focused on the development of automated synthesis systems, 99mTc-analog kits with regard to patient as well as operator safety.
Conference papers on the topic "68Ga generator"
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Sipila, Hannu T., Henri J. Sipila, Jan-Olof Lill, and Sven-Johan Heselius. "Determination of68Ge-trace activities in68Ga eluates from a68Ge/68Ga generator using X-ray spectrometry with a gas proportional counter." In 2009 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2009). IEEE, 2009. http://dx.doi.org/10.1109/nssmic.2009.5402032.
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Salas-Tapia, Luis Fernando, and Tian Zhang. "Production of Cyclotron-Based Gallium-68 With Low Energy Protons: Preliminary Target Design and Cyclotron Shielding Considerations." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65064.
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Abstract Nuclear reactors, cyclotrons and generators are being used to produce nuclear medicine radionuclides. Radiopharmaceuticals based on Gallium-68 are widely used both experimentally and clinically in Positron Emission Tomography (PET). Currently Ga-68 is mainly produced via 68Ge/68Ga generators, which are expensive. An alternative method is by cyclotron using high enriched Zinc-68 via the 68Zn(p,n)68Ga reaction. Investigations have been conducted for producing Ga-68 using a solid target impacted with a proton beam in energies between (13–14) MeV or higher. The main interest of this work is to produce Ga-68 using energies within a lower range, therefore Ga-68 can be accessed to locations with cyclotrons of lower energy. In this article, an approach to a novel target design to get Ga-68 with low energy protons is conducted. Adequate shielding to avoid extra doses outer the cyclotron is also considered. Monte Carlo code FLUKA is used to simulate the processes of interaction of radiation with matter and the radioactive isotope production. For a beam energy of 11 MeV and current on target of 40 μA the simulated produced activity is about 69.1 GBq. The results show the feasibility of producing Ga-68 with low energy protons and self-shielding system guarantees the regulation-based dose exposition outer the cyclotron.
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"nForce 680i and 680a NVIDIA's next generation platform processors." In 2007 IEEE Hot Chips 19 Symposium (HCS). IEEE, 2007. http://dx.doi.org/10.1109/hotchips.2007.7482516.
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