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      124I production for PET imaging at a cyclotron Translated title: Zyklotron Produktion von 124I für die PET Bildgebung

      1 , , , 2 , 1
      Carl Hanser Verlag

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          We here present a method for the production of Iodine-124 using a cyclotron. With this method, it will be possible to produce clinically relevant amounts of 124I with high chemical and radionuclidic purity for both diagnostic and therapeutic applications. The electroplated TeO 2 targets were irradiated with 29.5 MeV protons at current of 39.5 μA for 3.8 h. The separation of the produced Iodine activity from the bulk target material was performed by ion exchange chromatography method. 124I positron emitter excitation functions via 124Te(p,n) 124I, 125Te(p,2n) 124I, 126Te(p,3n) 124I, 124Te(d,2n) 124I, 121Sb(a,n) 124I and natTe(p,xn) 124I reactions were calculated by ALICE/ASH 0.1 (GDH Model & Hybrid Model) and TALYS-1.2 codes and compared to existing data. Theoretical calculation of production yield and calculation of target thickness requirement were obtained by TALYS-1.2 and SRIM codes for each reaction.


          Es wird eine Methode beschrieben für die Produktion von Iod-124 mit Hilfe eines Zyklotrons. Mit Hilfe dieser Methode wird es möglich sein klinisch relevante Mengen Iod-124 mit hoher chemischer Reinheit und Radionuklidreinheit für diagnostische und therapeutische Anwendungen zu erzeugen. TeO 2 Targets wurden mit 29.5 MeV Protonen bei Strömen von 39.5 μA für 3.8 h bestrahlt. Die Abtrennung der erzeugten Iod Aktivität vom Targetmaterial erfolgte mit Hilfe der Ionentauscher-Chromatographiemethode. Die 124I Positronenemitteranregungsfunktionen via 124Te(p,n) 124I, 125Te(p,2n) 124I, 126Te(p,3n) 124I, 124Te(d,2n) 124I, 121Sb(a,n) 124I and natTe(p,xn) 124I Reactionen wurden mit Hilfe der ALICE/ASH 0.1 (GDH Model & Hybrid Model) und TALYS-1.2 Codes berechnet und mit vorhandenen Daten verglichen. Die theoretische Berechnung der Produktionsausbeute und die Berechnung der erforderlichen Targetdicke wurde mit Hilfe des ALYS-1.2 und des SRIM Codes für jede Reaktion durchgeführt.

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          Most cited references40

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          Assay of plasma insulin in human subjects by immunological methods.

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            Quantitative imaging of iodine-124 with PET.

            PET is potentially very useful for the accurate in vivo quantitation of time-varying biological distributions of radiolabeled antibodies over several days. The short half-lives of most commonly used positron-emitting nuclides make them unsuitable for this purpose. Iodine-124 is a positron emitter with a half-life of 4.2 days and appropriate chemical properties. It has not been widely used because of a complex decay scheme including several high energy gamma rays. However, measurements made under realistic conditions on several different PET scanners have shown that satisfactory imaging and quantitation can be achieved. Whole-body and head-optimized scanners with different detectors (discrete BGO, block BGO and BaF2 time-of-flight), different septa and different correction schemes were used. Measurements of resolution, quantitative linearity and the ability to quantitatively image spheres of different sizes and activities in different background activities were made using phantoms. Compared with conventional PET nuclides, resolution and quantitation were only slightly degraded. Sphere detectability was also only slightly worse if imaging time was increased to compensate for the lower positron abundance. Quantitative imaging with 124I appears to be possible under realistic conditions with various PET scanners.
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              Radioimmunoimaging with longer-lived positron-emitting radionuclides: potentials and challenges.

              Radioimmunoimaging and therapy has been an area of interest for several decades. Steady progress has been made toward clinical translation of radiolabeled monoclonal antibodies for diagnosis and treatment of diseases. Tremendous advances have been made in imaging technologies such as positron emission tomography (PET). However, these advances have so far eluded routine translation into clinical radioimmunoimaging applications due to the mismatch between the short half-lives of routinely used positron-emitting radionuclides such as (18)F versus the pharmacokinetics of most intact monoclonal antibodies of interest. The lack of suitable positron-emitting radionuclides that match the pharmacokinetics of intact antibodies has generated interest in exploring the use of longer-lived positron emitters that are more suitable for radioimmunoimaging and dosimetry applications with intact monoclonal antibodies. In this review, we examine the opportunities and challenges of radioimmunoimaging with select longer-lived positron-emitting radionuclides such as (124)I, (89)Zr, and (86)Y with respect to radionuclide production, ease of radiolabeling intact antibodies, imaging characteristics, radiation dosimetry, and clinical translation potential.

                Author and article information

                Carl Hanser Verlag
                : 77
                : 1
                : 45-49
                1 Agricultural, Medical and Industrial Research School, Nuclear Science and Technology Research Institute, P.O. Box: 31485/498, Karaj, Iran
                2 Iranian Applied Research Center for Public Health and Sustainable Development, North Khorasan University of Medical Sciences, Bojnurd, Iran
                Author notes
                © 2012, Carl Hanser Verlag, München
                : 09 December 2010
                Page count
                References: 47, Pages: 5
                Self URI (journal page): https://www.hanser-elibrary.com/loi/kt
                Technical Contributions/Fachbeiträge

                Materials technology,Materials for energy,Nuclear physics
                Materials technology, Materials for energy, Nuclear physics


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