a ELEX Commerce, Bulevar Mihajla Pupina 10Z/IV pp 29, 11070 Novi Beograd, Serbia
b Ion Beam Applications SA, Chemin du cyclotron 3, 1348 Louvain-la-Neuve, Belgium

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1 Department of Medical Technology and Physics, Sir Charles Gairdner Hospital, Perth, Western Australia 2 School of Physics, University of Western Australia, Nedlands, Western Australia

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The authors whose names are listed immediately below certify that they have NO affi liations with or involvement in any organization or entity with any financial interest (such as honoraria; educational grants; participation in speakers’ bureaus; membership, employment, consultancies, stock ownership, or other equity interest; and expert testimony or patent-licensing arrangements), or non-fi nancial interest (such as personal or professional relationships, affi liations, knowledge or beliefs) in the subject matter or materials discussed in this manuscript.

Introduction
Radiopharmaceuticals labelled with 68Ga (half-life 68.0 minutes) and 89Zr (half-life 78.4 hours) are of considerable interest in positron emission tomography. The radionuclides are cyclotron-produced but unwanted nuclear reactions cre-ate longer-lived impurities, which may impact adversely on labelling efficiency, image quality and patient radiation dose.
The purpose of this study was to identify and quantify impurity radionuclides in the trial pro-duction of 68Ga and 89Zr.

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The excitation functions of the deuteron-induced nuclear reactions on the naturally monoisotopic gold were carefully re-measured using the stacked-foil technique up to 20 MeV. The isotopic cross-sections were obtained for the formation of Hg-197m, Hg-197g, Au-196m2, Au-196m1+g, Au-198-m and Au-198m+g. The results were compared with previous measurements and prediction of the nuclear reaction model code TALYS adopted from the TENDL-2017 library. We often observed significant discrepancy between our data and the predicted values, while the agreement with previous measurements varied from good consistency up to large difference. Obviously, the (d,2n) reaction enhances formation of the Hg-197m compared with the (p,n) reaction.

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The CRAB2RABBIT system was developed to complement the new radiochemical laboratories at the recently commissioned cyclotron TR-24. It covers and automatically controls all the steps of the labelled compound’s production, starting with the transport of a solid target to the cyclotron, followed by loading to the target holder, unloading after the irradiation, transport to the selected hot cell, dissolving, radionuclide separation/purification and labelling/purification. The system enables processing of solid targets, in particular for production of radiometals.

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The Advanced Research Clinical Center is a facili-ty established in June 2016 to restore Fukushima region from the disaster of the Fukushima Daiichi Nuclear Power Plant in 2011. This center manu-factures and various medical radioisotopes for cutting-edge diagnosis and treatment in Fuku-shima are. We have using two cyclotrons devel-oped by Sumitomo Heavy Industries, Ltd. The compact cyclotron MP-20S-V is mainly used for diagnostic RI production and clinical application. 11C, 13N, 15O and 18F are manufactured on a regu-lar basis and are used as clinical radiopharma-ceuticals such as 18FDG, 11C-PIB, 13NH3, 15O gas for patients. This cyclotron can also be used for research purposes and produces 64Cu, 89Zr, 124I and so on. The medium-sized cyclotron MP-30 is a new type of accelerator capable of accelerat-ing alpha beam up to 30 MeV. The MP-30 accel-erates three types of beams p, d, and a and is mainly used for research purposes. Up to now, 65Zn, 99mTc, 68Ge, 177Lu, and 211At have been pro-duced. As there is a need for using alpha emit-ters for tumor therapy, we are primarily focused on the manufacture of 211At for the application of target alpha therapy.

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Introduction: Competing nuclear reactions sometimes dictate that the beam energy incident on the target should be lower than the nominal beam energy of medical cyclotrons (i.e. Sc-44 at 11 MeV to reduce Sc-43 and Sc-44m; Ga-68 at 14 MeV to reduce Ga-66 and Ga-67). To ensure proper degrader thickness, it is important to precisely know the incident energy so as to minimize competing nuclear reactions while maximizing the energy available for desired nuclear reactions. Solid targets at the University of Iowa are at the end of the GE PETtrace beam line. While we believe there to be minimal energy loss down the beam line, we decided to measure the beam energy at the end of the beam line before designing our solid targets.

Methods: The GE paper burn target was modified with a new back flange that accepts foil stacks to determine the beam incident energy using the technique previously published by Gagnon (Appl Radiat Isot. 2011). Foil measurements were made using both 0.875 mm and 1.0 mm aluminum spacers.

Results: The beam energy at the end of the PETtrace beam line was measured to be 15.8 MeV.

Conclusion: The beam energy at the end of the PETtrace beam line was successfully measured, allowing for optimization of target design when a lower incident energy is needed.

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