Bibliografias temáticas / Radioisotopes

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Literatura científica selecionada sobre o tema "Radioisotopes"

Autor: Grafiati
Publicado: 4 de junho de 2021
Última modificação: 29 de julho de 2024

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Artigos de revistas sobre o assunto "Radioisotopes"

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Kilian, Krzysztof, e Krystyna Pyrzyńska. "Scandium Radioisotopes—Toward New Targets and Imaging Modalities". Molecules 28, n.º 22 (19 de novembro de 2023): 7668. http://dx.doi.org/10.3390/molecules28227668.

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The concept of theranostics uses radioisotopes of the same or chemically similar elements to label biological ligands in a way that allows the use of diagnostic and therapeutic radiation for a combined diagnosis and treatment regimen. For scandium, radioisotopes -43 and -44 can be used as diagnostic markers, while radioisotope scandium-47 can be used in the same configuration for targeted therapy. This work presents the latest achievements in the production and processing of radioisotopes and briefly characterizes solutions aimed at increasing the availability of these radioisotopes for research and clinical practice.
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Motahari, Sayed Mahdi, e Fatemah Alemzada. "Radiopharmaceuticals: Production, Physics, and Clinical Applications in Nuclear Medicine: A Short Review". Afghanistan Journal of Basic Medical Science 2, n.º 2 (15 de abril de 2024): 43–52. http://dx.doi.org/10.62134/ajbms/v2.i2.khatamuni.6.

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Introduction: The use of radioactive atoms in medicine is growing, particularly in nuclear medicine, where radiation is emitted from the body. Radiopharmaceuticals or radiotracers are artificial short-living radioisotopes labeled with special pharmaceuticals. There are around 1800 radioisotopes, but only around 200 are suitable for general applications. There are four methods for generating radioisotopes: reactor-producing, neutron activation, charged acceleration, and radioisotope generators. Cyclotrons are used to produce many other radioisotopes for medical applications. Physical and biomedical characteristics are crucial for radiopharmaceuticals for clinical use. Physical aspects include the type and energy of radiation, mother and daughter radioactive elements, purity, and half-life of radioactives. Biomedical considerations include easy adhesion to biomolecules, a dynamic time course in the body, toxicity, and high tissue targeting. Radiopharmaceuticals used in diagnosis differ from those used in therapy, with positron emission tomography (PET) using radioisotopes, and gamma-emitting radioisotope-labeled radiopharmaceuticals suitable for SPECT imaging. Over 90% of radiopharmaceuticals are used for diagnostic purposes. Conclusion: Nuclear medicine, as an inevitable part of modern medicine, follows different methods to create more effective diagnostic and therapeutic radiopharmaceuticals with respect to several physical and biological considerations.
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Pimlott, Sally L. "Radioisotopes for medical imaging". International Journal of Modern Physics A 29, n.º 14 (26 de maio de 2014): 1441003. http://dx.doi.org/10.1142/s0217751x14410036.

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Nunes, Bruno Silveira, Enio Rodrigo Fernandes Rodrigues, Jonathan Alexander Prestes Fruscalso, Roger Pizzato Nunes, Alexandre Bonatto e Mirko Salomón Alva-Sánchez. "Highly Enriched Uranium-Free Medical Radioisotope Production Methods: An Integrative Review". Applied Sciences 12, n.º 24 (8 de dezembro de 2022): 12569. http://dx.doi.org/10.3390/app122412569.

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The ever-growing need for radiopharmaceuticals, i.e., compounds containing pharmaceutical drugs and radioisotopes used for medical diagnostic imaging (SPECT/PET scan) and treating neoplasms, is significantly leading to an increased demand for such substances in hospitals and clinics worldwide. Currently, most large-scale productions of radioisotopes required for radiopharmaceuticals are carried out in research reactors, via the fission of highly enriched uranium. However, because large amounts of radioactive waste are produced as byproducts in this process, new greener methods are needed for radioisotope production. This work presents an integrative literature review and summarizes enriched uranium-free methods for radioisotope production, accomplished through the adoption of new reaction routes, distinct acceleration technologies, or by using other physical processes. This review considered forty-eight studies published from 2010 to 2021 on three established virtual databases. Among these selected works, a cyclotron is the most adopted HEU-free method for radioisotope production, and 44Sc, 68Ga, and 99mTc are the medical radioisotopes most often reported as produced by using the investigated HEU-free production methods.
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Perini, Efrain Araujo, Mikhail Skopchenko, Tran Thu Hong, Rahmat Harianto, Alexis Maître, Maidelys Rosa Rodríguez Rodríguez, Nathalia de Oliveira Santos et al. "Pre-feasibility Study for Establishing Radioisotope and Radiopharmaceutical Production Facilities in Developing Countries". Current Radiopharmaceuticals 12, n.º 3 (1 de outubro de 2019): 187–200. http://dx.doi.org/10.2174/1874471012666190328164253.

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Background:A significant number of developing countries have no facilities to produce medical radioisotopes and radiopharmaceuticals.Objective:In this paper we show that access to life-saving radioisotopes and radiopharmaceuticals and the geographical distribution of corresponding infrastructure is highly unbalanced worldwide.Methods:We discuss the main issues which need to be addressed in order to establish the production of radioisotopes and radiopharmaceuticals, which are especially important for developing countries as newcomers in the field. The data was gathered from several sources, including databases maintained by the International Atomic Energy Agency (IAEA), World Health Organization (WHO), and other international organizations; personal interactions with representatives in the nuclear medicine field from different regions of the world; and relevant literature.Results:Developing radioisotope and radiopharmaceutical production program and installing corresponding infrastructure requires significant investments, both man-power and financial. Support already exists to help developing countries establish their medical radioisotope production installations from several organizations, such as IAEA.Conclusion:This work clearly shows that access to life-saving radioisotopes and the geographical distribution of corresponding infrastructure is highly unbalanced. Technology transfer is important as it not only immediately benefits patients, but also provides employment, economic activity and general prosperity in the region to where the technology transfer is implemented.
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Konefał, Adam, Andrzej Orlef e Maria Sokół. "Application of therapeutic linear accelerators for the production of radioisotopes used in nuclear medicine". Polish Journal of Medical Physics and Engineering 28, n.º 3 (28 de julho de 2022): 107–16. http://dx.doi.org/10.2478/pjmpe-2022-0013.

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Abstract This review paper summarizes the possibilities of the use of therapeutic linear electron accelerators for the production of radioisotopes for nuclear medicine. This work is based on our published results and the thematically similar papers by other authors, directly related to five medical radioisotopes as 99Mo/99mTc, 198Au, 186Re, 188Re, 117mSn, produced using therapeutic linacs. Our unpublished data relating to the issues discussed have also been used here. In the experiments, two types of radiation were included in the analysis of the radioisotope production process, i.e. the therapeutic twenty-megavolt (20 MV) X-rays generated by Varian linacs and neutron radiation contaminating the therapeutic beam. Thus, the debated radioisotopes are produced in the photonuclear reactions and in the neutron ones. Linear therapeutic accelerators do not allow the production of radioisotopes with high specific activities, but the massive targets can be used instead. Thus, the amount of the produced radioisotopes may be increased. Apart from linear accelerators, more and more often, the production of radioisotopes is carried out in small medical cyclotrons. More such cyclotrons are developed, built, and sold commercially than for scientific research. The radioisotopes produced with the use of therapeutic linacs or cyclotrons can be successfully applied in various laboratory tests and in research.
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Kambali, Imam, Indra Saptiama e Hari Suryanto. "Residual Radioisotopes Generated from Neutron Irradiated Aluminum Capsules". Aceh International Journal of Science and Technology 6, n.º 3 (31 de dezembro de 2017): 104–10. http://dx.doi.org/10.13170/aijst.6.3.8116.

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Aluminum (Al) is often used to house a molybdenum oxide (MoO3) target for neutron or proton-produced technetium-99m (99mTc) radioisotope. During neutron or proton bombardment of an Al body, residual radioisotopes could be generated following nuclear reactions between the incoming particles and the Al body. In this research, residual radioisotopes produced following nuclear reactor based-neutron irradiation of Al body were experimentally measured using a portable gamma ray spectroscopy system; whereas TALYS 2015 calculated data were used to evaluate various nuclear reactions for the by-product identification. As a comparison, Al body used in a cyclotron-based 99mTc production was also analyzed. Experimental data indicated that relatively long-lived radioisotopes such as 26Al, 22Na and 24Na were identified in the Al body following nuclear reactor-based 99mTc production, whereas the presence of 27Mg radioisotope was, for the first time, experimentally detected in both the Al bodies for nuclear reactor-based and cyclotron-based 99mTc production. A special safety attention should be paid to the radiation workers when producing 99mTc using a nuclear reactor since it generates 26Al (half life = 716,600 years).
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Lapi, Suzanne E., e Jonathan W. Engle. "Radiochlorine: an underutilized halogen tool". Radiochimica Acta 107, n.º 9-11 (25 de setembro de 2019): 1027–31. http://dx.doi.org/10.1515/ract-2019-0015.

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Abstract Halogen radioisotopes have a variety of physical half-lives which are suitable for probing a wide variety of pharmacokinetic processes. Compared with other radiohalogens, relatively little work has been done with radiochlorine. However, high specific activity radioisotopes of chlorine are available from low energy cyclotron production in quantities suitable for positron emission tomography (PET) and fundamental research. In particular, the sole radioisotope of chlorine which may be used for PET imaging, 34mCl, has achieved a state of development that permits imaging in clinical settings though sparse research effort has been focused on this isotope over the last 40 years. Additionally, the other longer-lived radioisotopes of chlorine will likely continue to show utility for more traditional radiotracer studies and chemistry development.
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Pellico, Juan, Jordi Llop, Irene Fernández-Barahona, Riju Bhavesh, Jesús Ruiz-Cabello e Fernando Herranz. "Iron Oxide Nanoradiomaterials: Combining Nanoscale Properties with Radioisotopes for Enhanced Molecular Imaging". Contrast Media & Molecular Imaging 2017 (2017): 1–24. http://dx.doi.org/10.1155/2017/1549580.

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The combination of the size-dependent properties of nanomaterials with radioisotopes is emerging as a novel tool for molecular imaging. There are numerous examples already showing how the controlled synthesis of nanoparticles and the incorporation of a radioisotope in the nanostructure offer new features beyond the simple addition of different components. Among the different nanomaterials, iron oxide-based nanoparticles are the most used in imaging because of their versatility. In this review, we will study the different radioisotopes for biomedical imaging, how to incorporate them within the nanoparticles, and what applications they can be used for. Our focus is directed towards what is new in this field, what the nanoparticles can offer to the field of nuclear imaging, and the radioisotopes hybridized with nanomaterials for use in molecular imaging.
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Usman, Ahmed Rufai, e Ibrahim Abdullahi Lawal. "PROGRESS IN NICKEL TARGET DESIGNS FOR DEUTERON IRRADIATION: A MILESTONE IN RADIOISOTOPE PRODUCTION OPTIMIZATION". FUDMA JOURNAL OF SCIENCES 6, n.º 5 (31 de outubro de 2022): 211–14. http://dx.doi.org/10.33003/fjs-2022-0605-1484.

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Medical radioisotopes play significant roles in nuclear medicine, particularly in tumor diagnosis and its therapy. Optimization in production of these important isotopes is very essential for the overall health of the target patients. In this work, we analyzed general trends in the use of various forms of nickel metal as target for radioisotopes production in nuclear accelerators. A careful study of all previously used forms of nickel metal in the literature up to 2016 indicate that different physical forms of the metal, such as its very high purity and impure forms, alloys, compounds and powdered forms have, over the years, been used for various radioisotope productions under deuteron irradiation route, each providing different production effect. The excitation functions of several useful radioisotopes could be studied under deuteron irradiation of nickel. In a recent experimental work by the authors, some very pure, thin nickel foils of natural isotopic composition were also used in form of stacked arrangement for deuteron irradiation. The study found that most of the recent studies on radioisotopes production cross sections use very high purity and solid nickel forms.
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Teses / dissertações sobre o assunto "Radioisotopes"

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PUPILLO, Gaia. "Radioisotopes production via accelerator for nuclear medicine applications". Doctoral thesis, Università degli studi di Ferrara, 2014. http://hdl.handle.net/11392/2388938.

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Egorov, Oleg B. "Automation of radionuclide separations and analysis by flow injection techniques /". Thesis, Connect to this title online; UW restricted, 1998. http://hdl.handle.net/1773/11617.

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Hou, Xinchi. "Cyclotron-based production of radioisotopes for medical imaging studies". Thesis, University of British Columbia, 2014. http://hdl.handle.net/2429/50862.

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The cyclotron-based ¹⁰⁰Mo(p,2n)⁹⁹mTc reaction has been proposed as an alternative method for solving the recent shortage of ⁹⁹mTc, which is the most commonly used radioisotope in nuclear medicine. With this production method, however, even if highly enriched molybdenum is used, various radioactive and stable isotopes can be produced simultaneously with ⁹⁹mTc and they may affect the diagnostic outcome and radiation dosimetry in human studies. The objective of this thesis was to investigate the feasibility of the cyclotron-based production of ⁹⁹mTc. Towards this aim, theoretical predictions and experimental measurements were performed to investigate the quantity and purity of cyclotron-produced technetium. In this thesis, the production cross sections and yields of cyclotron-produced ⁹⁹mTc and various other radioactive and stable isotopes were calculated. Radiation doses from three radiopharmaceuticals labeled with cyclotron-produced technetium were estimated. Different conditions were considered for both yield and dosimetry calculations in order to investigate the optimal reaction parameters for producing maximum ⁹⁹mTc and minimizing other contaminants. To facilitate the complex and time-consuming calculations, a graphical user interface was developed allowing users to perform the theoretical predictions in only a few seconds. Besides theoretical estimations, quantitative experimental measurements of ⁹⁹mTc samples were performed. Gamma spectra from different cyclotron runs were analyzed. In order to investigate the image qualities for using cyclotron-produced technetium, phantom scans for both cyclotron- and reactor-produced ⁹⁹mTc at different times after end of beam were performed using SPECT. Large quantities of produced ⁹⁹mTc proved the capability of cyclotron production of ⁹⁹mTc. Both theoretical predictions and experimental analysis showed over 9 Ci of ⁹⁹mTc can be produced in a 6 hours cyclotron run when using enriched ¹⁰⁰Mo target. Besides ⁹⁹mTc, the main contributors, which influenced the production activities, patient doses and quality of images, were ⁹⁴g⁻⁹⁶gTc. These results indicated the molybdenum target used in cyclotron production should have relatively small content of ⁹⁵⁻⁹⁷Mo, which are the “reaction parents” for ⁹⁴g⁻⁹⁶gTc. Furthermore, we demonstrated that incident proton beam energies in the range of 16-19 MeV, target thicknesses degrading beam energy to 10 MeV and relatively short irradiation times (3-6 hours) corresponded to the most advantageous region for ⁹⁹mTc production.
Science, Faculty of
Physics and Astronomy, Department of
Graduate
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Sitarz, Mateusz. "Research on production of new medical radioisotopes with cyclotron". Thesis, Nantes, 2019. http://www.theses.fr/2019NANT4050.

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Aujourd’hui, les radio-isotopes sont fréquemment utilises en médecine, pour le diagnostic et la thérapie. Cependant, le développement constant de la médecine nucléaire provoque l’application de nouveaux radio-isotopes médicaux. La recherche sur leur production possible a grande échelle est la première étape d’un long processus d’études avant de pouvoir de les utilise dans des essais cliniques. Dans cette thèse, les voies de production ont été étudiées pour la formation de médicalement intéressants 43Sc, 44m,gSc, 47Sc, 97Ru et 105Rh en utilisant de cyclotrons. Les radioisotopes de scandium ont ete produits avec des cibles en calcium et en titane et avec des faisceaux de protons ou de deuterons; 97Ru a ete obtenu par irradiation de molybdene avec des particules α; et la production de 105Rh a ete etudiee avec des cibles en ruthenium et avec un faisceau de deuteron. Deux grandeurs ont été déterminés expérimentalement: la section efficace de réaction nucleaire, σ(E), et l’efficacité de la production, TTY(E), qui ont été utilisés pour discuter des conditions possibles de production optimale à grande échelle de ces radio-isotopes. De plus, la conversion de σ(E) en TTY(E) a été automatisée en développant un logiciel spécialisé, et un algorithme de reconstruction de σ(E) avec des valeurs de TTY(E) a été introduit
Today, radioisotopes are commonly used in medicine, both in diagnosis and therapy. However, steady development of nuclear medicine demands the application of new medical radioisotopes. The investigation of their possible large-scale production is a first step in a long research process before they can be used in clinical trials. In this thesis, the production routes were studied for the formation of medically interesting 43Sc, 44m,gSc, 47Sc, 97Ru, and 105Rh with the use of cyclotrons. The scandium radioisotopes were produced with calcium and titanium targets and proton or deuteron beams; 97Ru was obtained through the irradiation of molybdenum with α particles; and production of 105Rh was studied with ruthenium targets and deuteron beam. Two parameters were determined experimentally: nuclear reaction cross-section, σ(E), and Thick Target Yield, TTY(E), which were used to discuss the possibility of optimal large-scale production conditions of discussed radioisotopes. Additionally, the conversion of σ(E) to TTY(E) was automatized by developing a dedicated software, and an algorithm for the reconstruction of σ(E) based on TTY(E) measurements was introduced
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de, Sousa Fernando Nuno. "Movement of radionuclides through unsaturated soils". Diss., Georgia Institute of Technology, 1985. http://hdl.handle.net/1853/17875.

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Pan, Xiaodi. "Radioisotopes in Domestic Wastewater and Their Fate in Wastewater Treatment". Digital WPI, 2016. https://digitalcommons.wpi.edu/etd-theses/1247.

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"Modern medical therapies involving radioisotopes provide radionuclide contamination in wastewater. These radioisotopes present in wastewater increase the possibility of human exposure to radiation. The objective of this work was to study the fate of radionuclides of medical sources in wastewater, and to determine the distribution of various radionuclides in different stages of wastewater treatment. Influent, return activated sludge and effluent samples were collected from four wastewater facilities in Massachusetts. Samples were collected approximately twice a month over 4 months. The radionuclides and their decay products were tested by inductively coupled plasma with mass spectrometry (ICP-MS) and broad energy germanium detector analysis (BEGe). The samples were analyzed to determine the content and radioactivity of each target radionuclide and decay product for three treatment stages (influent, return activated sludge and effluent) from each facility at different sampling times. The results indicated that I-131 is the only radionuclide in wastewater, however many decay products were identified. Recommendations are put forward according to the testing results."
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Naidoo, Clive. "Selective separation of elements and radioisotopes by ion exchange chromatography". Thesis, Stellenbosch : Stellenbosch University, 2002. http://hdl.handle.net/10019.1/53046.

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Thesis (PhD)--Stellenbosch University, 2002.
ENGLISH ABSTRACT: The equilibrium distribution coefficients of 32 metal ions [Al(llI), As(V), CdïIl), Ce(III), Ce(IV), Co(n), Cr(III), Cu(II), Fe(III), Ga(III), Ge(IV), !n(III), La(III), Mn(II), Mo(VI), Nb(V), Ni(II), Pr(III), Sb(V), Sc(III), Se(IV), Sn(IV), Ta(V), Tb(III), Te(IV), Ti(IV), Vev), W(VI), Y(III), Yb(III), Zn(lI) and Zr(IV)] on a cation exchanger (Bio- Rad® AG50W-X8) and an anion exchanger (Bio-Rad® AG1-X8) in varying oxalic acid - sulphuric acid mixtures were successfully determined. The equilibrium distribution coefficients of these selected metal ions were determined in both 0.05 M and 0.25 M oxalic acid at various concentrations of sulphuric acid (0.005 M, 0.05 M, 0.10 M, 0.25 M, 0.50 M, 1.00 M, 1.50 M and 2.00 M). Attempts to explain the sorption behaviour of the selected metal ions were made by using MINEQL+, a speciation modelling program, and the speciation systems for AI(III), Cd(II), Co(II) and Zn(lI) in varying oxalic acid - sulphuric acid mixtures were determined. Two component [Zr(IV)-La(III); AI(III)-La(III); Ga(IlI)-Zn(II); As(V)-Zn(II); Cu(II)- Ce(IV); Ga(III)-Ce(IV); Ge(IV)-Ce(III); Mo(VI)- Y(III); Nb(V)- Y(III); Ga(III)-Co(II); As(V)-Co(lI) and Fe(III)-Mn(II)] and three component [Fe(III)-Ga(III)-Zn(lI) and Zr(IV)-Ta(V)-Yb(III)] mixtures on a 10 ml or 13 ml cation exchange resin in a variety of oxalic acid - sulphuric acid mixtures were successfully separated. Two component [As(V)-Zr(IV); Co(II)-Fe(III); Ni(II)-Co(lI) and Ni(II)-Fe(III)] and three component [Ni(II)-As(V)-Se(IV); AI(III)-Zn(II)-Ge(IV) and As(V)-Cu(II)-Ge(IV)] mixtures on a 10 ml or 13 ml anion exchange resin in a variety of oxalic acid - sulphuric acid mixtures were also successfully separated and studied. It was also shown how some of the elution curves developed above could easily be adapted for radiochemical separations. Usin~ the relevant data from the above study, a separation for 68Gefrom a Ga20 target was developed according to a method based on acid dissolution of the target and chromatography on an anion exchange resin (Bio-Rad® AG1-X8). The separated 68Geshowed high radionuclidic purity and an acceptable chemical purity.
AFRIKAANSE OPSOMMING: Die ewewigsverdelingskoëffisiënte van 32 metaalione [Al(III), As(V), Cd(II), Ce(III), Ce(IV), Co(II), Cr(III), Cu(II), Fe(III), Ga(III), Ge(IV), In(III), La(III), Mn(ll), Mo(VI), Nb(V), Ni(ll), Pr(Ill), Sb(V), Sc(III), Se(IV), Sn(IV), Ta(V), Th(Ill), Te(IV), Ti(IV), vrv; W(VI), Y(III), Yb(III), Zn(lI) en Zr(IV)] op 'n katioonruiler (Bio-Rad® AG50W-X8) en 'n anioonruiler (Bio-Rad® AG1-X8) in veranderende oksaalsuurswaelsuurmengsels is met welslae bepaal. Die ewewigsverdelingskoëffisiënte van hierdie geselekteerde elemente is in beide 0.05 Men 0.25 M oksaalsuur by verskeie konsentrasies swaelsuur (0.005 M, 0.05 M, 0.10 M, 0.25 M, 0.50 M, 1.00 M, 1.50 M en 2.00 M) bepaal. Daar is gepoog om die sorpsiegedrag van die geselekteerde metaalione te verklaar deur die gebruik van MINEQL+, 'n spesiëringmodelleringsprogram, en die spesiëringsisteme vir AI(III), Cd(II), Co(II) en Zn(lI) in veranderende oksaalsuur-swaelsuurmengsels is bepaal. Tweekomponent [Zr(IV)- La(III); AI(III)-La(II!); Ga(III)-Zn(Il); As(V)-Zn(II); Cu(II)-Ce(IV); Ga(III)-Ce(IV); Ge(IV)-Ce(Il!); Mo(VI)- Y(III); Nb(V)- Y(ll!); Ga(Ill)-Co(Il); As(V)-Co(lI) en Fe(III)- Mn(II)] en driekomponent [Fe(III)-Ga(III)-Zn(ll) en Zr(IV)- Ta(V)- Yb(III)] mengsels op 'n 10 ml of 13 ml katioonruilhars in 'n verskeidenheid oksaalsuurswaelsuurmengsels is met welslae geskei. Tweekomponent [As(V)-Zr(IV); Co(II)- Fe(III); Ni(Il)-Co(lI) en Ni(II)-Fe(III)] en driekomponent [Ni(II)-As(V)-Se(IV); AI(III)-Zn(Il)-Ge(IV) en As(V)-Cu(II)-Ge(IV)] mengsels op 'n 10 ml of 13 ml anioonruilhars in 'n verskeidenheid oksaalsuur-swaelsuurmengsels is ook met welslae geskei en bestudeer. Daar is ook aangetoon hoe sommige van die elueringskrommes wat hierbo ontwikkel is, maklik vir radiochemiese skeidings aangepas sou kon word. Deur gebruik te maak van die relevante data uit die studie hierbo, is 'n skeiding vir 68Geuit 'n Ga20-teiken ontwikkel volgens 'n metode gebaseer op suurdissolusie van die teiken en chromatografie op 'n anioonruilhars (Bio-Rad® AG1-X8). Die geskeide 68Gehet hoë radionukliedsuiwerheid en 'n aanvaarbare chemiese suiwerheid getoon.
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MARTINI, Petra. "High-Yield Cyclotron Production of Metallic Radioisotopes for Nuclear Medicine". Doctoral thesis, Università degli studi di Ferrara, 2018. http://hdl.handle.net/11392/2487885.

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The main purpose of LARAMED project (LAboratoty of Radioisotopes for MEDicine), founded at LNL-INFN, is the R&D on cyclotron production of conventional, such as Tc-99m (TECHN-OSP projects), and emerging, such as Cu-67 (COME project), metallic medical radioisotopes. The aim of my PhD has been the development, optimization and automation of post-irradiation target processing systems, enabling to recover in high yield highly pure radioisotopes (RI), one of the most critical steps in the RI cyclotron production. The possibility of a reactor-produced molybdenum-99 shortage, used as parent nuclide of in 99Mo/99m Tc generators, is still a potential scenario. The direct cyclotron-production of Tc-99m through the (p,2n) reaction on a Mo-100 target seemed to be a reliable solution. In the framework of TECHN-OSP project, a technology for enabling the in-hospital cyclotron self-production of Tc-99m, in order to afford the availability of the most used radiometal in diagnostic applications in case of shortages, has been developed. The Tc-99m cyclotron-production optimization included the design of a solid target, the development of an automatic module for target processing and enriched target material recovery study. In this thesis, the description of Tc-99m production experiments, performed in collaboration with the Sant’Orsola Hospital in Bologna, and the development of the automatic module for target processing, are well detailed. During my PhD I had the opportunity to collaborate with the Canadian research group at TRIUMF (Vancouver, CA), also working on Tc-99m cyclotron-production, by contributing at the optimization and automation of molybdenum target dissolution and purification procedure of cyclotron-produced Tc-99m. In this thesis a comparison between the two developed, Italian and Canadian, target processing setup is also reported. Alongside that, I have collaborated to COME project whose purpose is the evaluation of the cyclotron production efficiency of Cu-67, a particularly interesting RI for its application in “theranostics”. The large scale cyclotron-production of this RI is still a poorly studied key point. In order to define the Cu-67 best cyclotron-production route, we focused our attention on unknown cross-section measurement of nuclear reactions on a Zn-70 target (35-70MeV energy range). Essential for this project was the development and optimization of a high yield separation and purification procedure of Cu-67 from the Zn-70 bulk and the co-produced Ga-67 contaminant that, having the same γ-lines of Cu-67 (both decay to Zn-67 with similar half-lives), poses a serious issue for the determination of the activity of Cu-67. The description of the experiments, performed in collaboration with ARRONAX, is reported in this thesis. Finally, the clinical needs of larger amount of the PET radiometal generator-produced Ga-68 prompted TRIUMF Life Sciences division to investigate Ga-68 cyclotron-production from liquid target since it is based on the existing medical-cyclotron network and technology. This technique will improve the availability of Ga-68 in hospitals housing an appropriate cyclotron by making them independent self-producers. Since the major problem affecting liquid targets is the contamination with radioactive/stable metals (e.g. iron) coming from the dissolution of some material from vacuum isolation or target body components during the irradiation, a separation and purification procedure together with a semi-automatic system, particularly focused on the purification of Ga-68 from Zn and Fe, have been developed. The main purpose is to obtain a final product suitable for medical use and to enable radiolabeling and in-vivo imaging studies with cyclotron produced 68Ga-DOTATOC.
Il progetto LARAMED (LAboratoty of Radioisotopes for MEDicine), fondato presso i LNL-INFN, ha come scopo l’R&D per la produzione da ciclotrone di radioisotopi metallici convenzionali, come il Tc-99m (progetto TECHN-OSP, ed emergenti, come il Cu-67 (progetto COME), per uso medicale. L'obiettivo del mio dottorato di ricerca è stato lo sviluppo, ottimizzazione e automazione di sistemi di processamento dei target irraggiati al fine di estrarre, in alta resa e purezza, il radioisotopo (RI) di interesse, uno dei passaggi più critici nella produzione da ciclotrone dei RI per la medicina. La possibilità di un’ulteriore crisi di produzione da reattori nucleari di Mo-99, nuclide genitore nei generatori Mo-99/Tc-99m, è ancora uno scenario possibile. La produzione diretta di Tc-99m da ciclotrone per mezzo della reazione nucleare Mo-100(p,2n) sembra essere una soluzione alternativa affidabile. Nell’ambito del progetto TECHN-OSP è stata sviluppata una tecnologia in grado di rendere le radiofarmacie delle Medicine Nucleari, che ospitano un ciclotrone appropriato, indipendenti nella produzione di Tc-99m al fine di sopperire ad ogni eventuale carenza nell’approvvigionamento dei generatori. L’ottimizzazione della produzione ha previsto la progettazione di un target, lo sviluppo di un modulo automatico per il processamento del target e lo studio del recupero del materiale arricchito costituente il target stesso. In questa tesi sono descritti i test di produzione di Tc-99m, eseguiti in collaborazione con l'ospedale Sant'Orsola di Bologna, ed in particolare lo sviluppo di un modulo automatico di processamento del target. Nel corso del dottorato, ho avuto l'opportunità di collaborare con il gruppo di ricerca canadese al TRIUMF (Vancouver, CA), anch’esso coinvolto nell’ottimizzazione della produzione di Tc-99m da ciclotrone, contribuendo all'ottimizzazione e automazione delle procedure di dissoluzione e purificazione di Tc-99m da target di Mo-100. In questa tesi viene anche riportato un confronto tra i due sistemi di processamento target da me sviluppati, in Italia e in Canada. Parallelamente ho collaborato al progetto COME il cui obiettivo risiede nella valutazione dell'efficienza di produzione di Cu-67 da ciclotrone, RI particolarmente interessante per le sue applicazioni in “teranostica”. La produzione da ciclotrone su larga scala di questo RI è ancora un punto chiave scarsamente studiato. Al fine di definire la migliore via di produzione di Cu-67, abbiamo focalizzato l’attenzione su misure di sezioni d’urto inedite (target Zn-70, protoni incidenti di energie 35-70MeV). Essenziale per questo progetto è stato lo sviluppo di un processo altamente efficiente di separazione di Cu-67 dal target e dal Ga-67, coprodotto che, avendo le stesse linee γ del Cu-67, crea problemi nella determinazione dell'attività di Cu-67. La descrizione degli esperimenti, eseguita in collaborazione con ARRONAX, è riportata in questa tesi. Infine, le esigenze cliniche di una maggiore quantità di Ga-68, RI PET attualmente prodotto da generatore Ge-68/Ga-68, hanno spinto il gruppo di ricerca del TRIUMF a studiare la produzione di Ga-68 da ciclotrone a partire da un target liquido di Zn-68, al fine di migliorare la disponibilità di Ga-68 negli ospedali che ospitano un ciclotrone appropriato rendendoli produttori indipendenti. Poiché il problema principale che colpisce la produzione da target liquido è la contaminazione da metalli (es. Fe) provenienti dalla degradazione di alcuni componenti del corpo del target, è stata sviluppata una procedura di separazione e purificazione del Ga-68 da Zn e Fe. Lo scopo principale è quello di ottenere un prodotto finale adatto all’uso medico e di consentire la radio-marcatura di (Ga-68)-DOTATOC e studi di imaging in vivo con Ga-68 prodotto da ciclotrone.
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9

Curtis, Nicola. "Tritium NMR studies of protein-ligand interactions". Thesis, University of Surrey, 1994. http://epubs.surrey.ac.uk/842983/.

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Tritium NMR studies provide a convenient way of obtaining detailed information about conformational equilibria, dynamic processes and specific interactions in protein-ligand complexes provided that suitably 3H-labelled molecules are available. In this study [7,9-3H]- and [3',5',7-3H]folic acid, and [3',5',7-3H]methotrexate were synthesised and the NMR spectra of their complexes with Lactobacillus casei dihydrofolate reductase (DHFR) were assigned and analysed as a function of pH (DHFR-folate complexes) and temperature (DHFR-methotrexate complexes). From these data it was possible to obtain further evidence about the orientation of the pteridine ring in the complexes, and to monitor the dynamic processes in the bound ligands. In the 3H NMR spectra of the ternary complexes of the 3H-labelled folic acids with DHFR and NADP+, each labelled tritium gave rise to multiple signals, confirming previous findings that there are three interconverting, pH dependent, conformational forms of bound folate (forms I, IIa and IIb) in the ternary complex. The folate benzoyl ring could be shown to be in essentially the same environment in the different forms with the major differences being associated with the pterin ring. The appearance of a single resonance for the 3',5'-tritons showed that the benzoyl ring is flipping rapidly in all three forms. In contrast, the methotrexate binary complex and also the ternary complex with NADPH were shown to exist as a single conformational state with the benzoyl ring flipping rate being too slow to give a single averaged signal for the 3',5'-tritium nuclei over the temperature range 283 - 313 K. 3h{1h} Nuclear Overhauser enhancement experiments have been conducted on the small molecules, [3H]dimethyl sulphoxide, [3',5',7-3H]folic acid and [3',5',7-3H]methotrexate as a prelude to 3H-1H heteronuclear NOE experiments on binary and ternary complexes formed using Lactobacillus casei DHFR and the ligands [3',5',7-3H]methotrexate and [3',5',7-3H]folic acid.
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Valsborg, Jacob Stenmann. "Design and synthesis of radioligands in drug development /". [Cph.] : Royal danish School of Pharmacy, Department of Medicinal Chemistry, 2002. http://www.dfh.dk/phd/defences/jacobvalsborg.htm.

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Livros sobre o assunto "Radioisotopes"

1

United States. Office of the Assistant Secretary for Nuclear Energy. Office of Support Programs., ed. Radioisotopes: Today's applications. [Washington]: U.S. Dept. of Energy, Assistant Secretary for Nuclear Energy, Office of Program Support, 1988.

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2

Mendes, Kassio Ferreira, ed. Radioisotopes in Weed Research. First edition. | Boca Raton, FL : CRC Press, 2021.: CRC Press, 2020. http://dx.doi.org/10.1201/9781003005070.

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3

Prelas, Mark, Matthew Boraas, Fernando De La Torre Aguilar, John-David Seelig, Modeste Tchakoua Tchouaso e Denis Wisniewski. Nuclear Batteries and Radioisotopes. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-41724-0.

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4

Gábor, Földiák, ed. Industrial application of radioisotopes. Amsterdam: Elsevier, 1986.

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5

M, Lewis S., e Bayly R. J, eds. Radionuclides in haematology. Edinburgh: Churchill Livingstone, 1986.

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6

H, Thrall James, e Swanson Dennis P, eds. Diagnostic interventions in nuclear medicine. Chicago: Year Book Medical Publishers, 1985.

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7

Agency, International Atomic Energy, ed. Radioisotope handling facilities and automation of radioisotope production. Vienna: International Atomic Energy Agency, 2004.

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8

Horton, P. W. Radionuclide techniques in clinical investigation. Ann Arbor, MI: UMI, 1998.

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9

J, Slater Robert, ed. Radioisotopes in biology: A practical approach. 2a ed. Oxford: Oxford University Press, 2002.

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10

J, Slater Robert, ed. Radioisotopes in biology: A practical approach. Oxford: Oxford University Press, 1990.

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Capítulos de livros sobre o assunto "Radioisotopes"

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Prelas, Mark, Matthew Boraas, Fernando De La Torre Aguilar, John-David Seelig, Modeste Tchakoua Tchouaso e Denis Wisniewski. "Radioisotopes". In Lecture Notes in Energy, 39–79. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-41724-0_2.

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Jasmin, Claude, Isabelle Resche, Françoise Bodéré, Caroline Rousseau e Jean-François Chatal. "Radioisotopes and Radioimmunoisotopes". In Textbook of Bone Metastases, 301–12. Chichester, UK: John Wiley & Sons, Ltd, 2006. http://dx.doi.org/10.1002/0470011610.ch23.

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Charlton, J. S. "Radioisotopes in industry". In Radioisotope Techniques for Problem-Solving in Industrial Process Plants, 1–8. Dordrecht: Springer Netherlands, 1986. http://dx.doi.org/10.1007/978-94-009-4073-4_1.

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Rayburn, Stephen R. "Hazards of Radioisotopes". In The Foundations of Laboratory Safety, 181–218. New York, NY: Springer New York, 1990. http://dx.doi.org/10.1007/978-1-4612-3320-6_14.

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Duggirala, Rajesh, Amit Lal e Shankar Radhakrishnan. "Radioactivity and Radioisotopes". In MEMS Reference Shelf, 1–12. New York, NY: Springer New York, 2010. http://dx.doi.org/10.1007/978-1-4419-6763-3_1.

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Hayes, Robert Bruce. "Applications of Radioisotopes". In Nuclear Energy, 395–410. New York, NY: Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_952.

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Hayes, Robert Bruce. "Applications of Radioisotopes". In Encyclopedia of Sustainability Science and Technology, 1–16. New York, NY: Springer New York, 2017. http://dx.doi.org/10.1007/978-1-4939-2493-6_952-1.

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Kloft, Werner J. "Radioisotopes in Vector Research". In Advances in Disease Vector Research, 41–66. New York, NY: Springer New York, 1992. http://dx.doi.org/10.1007/978-1-4612-2910-0_2.

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Yue, Ziming, e Te-Ming Tseng. "Historical use of radioisotopes in weed research". In Radioisotopes in Weed Research, 1–16. First edition. | Boca Raton, FL : CRC Press, 2021.: CRC Press, 2020. http://dx.doi.org/10.1201/9781003005070-1.

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Mendes, Kassio Ferreira, Rodrigo Nogueira de Sousa, Matheus Bortolanza Soares, Douglas Gomes Viana e Adijailton Jose de Souza. "Sorption and desorption studies of herbicides in the soil by batch equilibrium and stirred flow methods". In Radioisotopes in Weed Research, 17–60. First edition. | Boca Raton, FL : CRC Press, 2021.: CRC Press, 2020. http://dx.doi.org/10.1201/9781003005070-2.

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Trabalhos de conferências sobre o assunto "Radioisotopes"

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Barklay, Chadwick, Emily Jane Watkinson, Richard Ambrosi, Ramy Mesalam, Alessandra Barco e Daniel Kramer. "Considerations for Utilising Alternative Radioisotopes in Radioisotope Power Systems". In 2021 IEEE Aerospace Conference. IEEE, 2021. http://dx.doi.org/10.1109/aero50100.2021.9438353.

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Adams, Thomas E., Jeffrey A. Webster e Rusi P. Taleyarkhan. "Electron and Material Interaction Studies for the Optimization of a Novel Tritium Based Radioisotope Power Source". In 17th International Conference on Nuclear Engineering. ASMEDC, 2009. http://dx.doi.org/10.1115/icone17-76046.

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Radiation interaction with materials can have beneficial uses, such as in radioisotope power sources where the ionizing particles provide a direct energy source for conversion into electricity; similar to photovoltaic cells. Radioisotope power sources in the past did not succeed: limited low power applications, rapid semi-conductor degradation, availability and cost of suitable radioisotopes. Now, the power generated is compatible with present electronic devices. Novel and compelling need-based applications for long-life radioisotope power sources are emerging in the military, intelligence, commercial and medical markets. However, the net efficiency is still below 10% due to the isotropic emission and self-shielding losses in the source, electron-hole recombination and interactions of a beta particle. Evaluating the effects of beta particle interaction with a p-n junction is the key to optimizing a betavoltaic cell design. The radioisotope source needs to be safe, robust and affordable; a design using tritium and a modified silicon structure could offer a comprehensive and optimal advance to the state-of-the art.
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Mohamadian, sM, S. A. H. Feghhi e H. Afarideh. "Analyze and Simulation of a Typical MEMS RPG Using MCNP Code". In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48766.

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Microbatteries are essential for portable electronics, cellular phones and MEMs devices to be miniaturized. Use of radioisotopes to realize nuclear microbatteries have been extensively researched. Electrical energy of a nuclear battery is produced from radioactive materials decaying by a suitable energy conversion process. Our approach in this paper is study of a direct collected charge to motion conversion. In this manuscript, the performance of radioisotope powered piezoelectric generator has been analyzed and simulated. The generator employs direct charging to convert radiated beta particles kinetic energy into stored electromechanical energy in a piezoelectric unimorph piezoelectricity to stored mechanical energy into extractable electrical energy.
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4

McDaniel, Floyd D., W. J. Courtney, W. W. Givens, W. B. Cloud, B. L. Freeman, Ivor Morgan e Richard Schafer. "Fast-neutron production of radioisotopes". In 4th International Conference on Applications of Nuclear Techniques: Neutrons and their Applications, editado por George Vourvopoulos e Themis Paradellis. SPIE, 1995. http://dx.doi.org/10.1117/12.204197.

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Ávila-Rodríguez, M. A., A. Zárate-Morales, A. Flores-Moreno, Ricardo Alarcon, Phil Cole, Andres J. Kreiner e Hugo F. Arellano. "Cyclotron Production of Medical Radioisotopes". In VIII LATIN AMERICAN SYMPOSIUM ON NUCLEAR PHYSICS AND APPLICATIONS. AIP, 2010. http://dx.doi.org/10.1063/1.3480203.

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NIELSEN, K. S., R. G. V. HANCOCK, L. G. I. BENNETT, W. J. LEWIS, W. S. ANDREWS, B. J. LEWIS e H. W. BONIN. "THE UNAVOIDABLE USE OF RADIOISOTOPES AT RMC". In Proceedings of the 3rd International Conference on Isotopes. WORLD SCIENTIFIC, 2000. http://dx.doi.org/10.1142/9789812793867_0011.

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PONSARD, BERNARD. "PRODUCTION OF RADIOISOTOPES IN THE BR2 REACTOR". In Proceedings of the 3rd International Conference on Isotopes. WORLD SCIENTIFIC, 2000. http://dx.doi.org/10.1142/9789812793867_0018.

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8

Howe, Steven D. "Micro Asteroid Prospector Powered by Energetic Radioisotopes: MAPPER". In SPACE TECHNOLOGY AND APPLICATIONS INT.FORUM-STAIF 2005: Conf.Thermophys in Micrograv;Conf Comm/Civil Next Gen.Space Transp; 22nd Symp Space Nucl.Powr Propuls.;Conf.Human/Robotic Techn.Nat'l Vision Space Expl.; 3rd Symp Space Colon.; 2nd Symp.New Frontiers. AIP, 2005. http://dx.doi.org/10.1063/1.1867243.

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9

Bindu, K. C., Frank Harmon, Valeriia N. Starovoitova, Jon Stoner e Douglas P. Wells. "Optimization of commercial scale photonuclear production of radioisotopes". In APPLICATION OF ACCELERATORS IN RESEARCH AND INDUSTRY: Twenty-Second International Conference. AIP, 2013. http://dx.doi.org/10.1063/1.4802359.

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Dejonghe, Paul. "Development of Radioactive Waste Management and Environmental Remediation Activities in Belgium". In ASME 2001 8th International Conference on Radioactive Waste Management and Environmental Remediation. American Society of Mechanical Engineers, 2001. http://dx.doi.org/10.1115/icem2001-1196.

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Abstract As of the 1950s the nuclear programme in Belgium was developed along three lines: • nuclear power generation, • nuclear fuel cycle and nuclear fuel fabrication, • production and application of radioisotopes.
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Relatórios de organizações sobre o assunto "Radioisotopes"

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Birnbaum, Eva R. Medical Radioisotopes. Office of Scientific and Technical Information (OSTI), julho de 2013. http://dx.doi.org/10.2172/1088916.

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Peaslee, Graham F., e Suzanne E. Lapi. Preparing for Harvesting Radioisotopes from FRIB. Office of Scientific and Technical Information (OSTI), fevereiro de 2015. http://dx.doi.org/10.2172/1170526.

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Lapi, Suzanne, e Graham Peaselee. Preparing for Harvesting Radioisotopes from FRIB. Office of Scientific and Technical Information (OSTI), maio de 2019. http://dx.doi.org/10.2172/1510280.

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Couture, Aaron J. Calorimeters for Capture Measurements on Radioisotopes. Office of Scientific and Technical Information (OSTI), abril de 2013. http://dx.doi.org/10.2172/1072250.

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Bennett, R. G. Markets for reactor-produced non-fission radioisotopes. Office of Scientific and Technical Information (OSTI), janeiro de 1995. http://dx.doi.org/10.2172/41373.

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Nelson, Noel, e Brad Johnson. A Comparison of the Radiation Shielding Requirements of Select Radioisotopes for Potential Use in Radioisotope Power Systems. Office of Scientific and Technical Information (OSTI), abril de 2023. http://dx.doi.org/10.2172/1989569.

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Litz, Marc. Semiconductor Energy Converter Calibration Laboratory for Betavoltaic Radioisotopes. DEVCOM Army Research Laboratory, agosto de 2023. http://dx.doi.org/10.21236/ad1209647.

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Mirzadeh, S., A. P. Callahan, F. F. Jr Knapp e R. E. Schenter. Production capabilities in US nuclear reactors for medical radioisotopes. Office of Scientific and Technical Information (OSTI), novembro de 1992. http://dx.doi.org/10.2172/7176237.

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Mirzadeh, S., A. P. Callahan, F. F. Jr Knapp e R. E. Schenter. Production capabilities in US nuclear reactors for medical radioisotopes. Office of Scientific and Technical Information (OSTI), novembro de 1992. http://dx.doi.org/10.2172/10191510.

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Abel, K. H., M. E. Panisko, W. K. Hensley, T. W. Bowyer e R. W. Perkins. Determination of atmospheric concentrations of xenon radioisotopes. Progress report. Office of Scientific and Technical Information (OSTI), julho de 1995. http://dx.doi.org/10.2172/95229.

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