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A new Center for Radiopharmaceutical Cancer Research was established at the Helmholtz-Zentrum Dresden-Rossendorf in order to centralize radionuclide production, radiopharmaceutical production and the chemical and biochemical research facilities in 2017. A routine production of several radionuclides was established during the last years. We report about the production methods of metallic and standard PET radionuclides like 11C, 18F, 123I, 64Cu, 67Cu, 67Ga, 131Ba and 131La that are done regularly. In the conclusion we report typical irradiation parameters and achieved saturation yields.

Proceedings of the 24TH TOPICAL CONFERENCE ON RADIO-FREQUENCY POWER IN PLASMAS 26–28 September 2022 Annapolis, USA, The viability of magnetic confinement fusion as an energy source depends on achieving the high ion temperatures required for D-T fusion. Among the available techniques, plasma heating with waves in the ion cyclotron range of frequencies (ICRF) is a prominent method for bulk ion heating in fusion plasmas. Furthermore, a detailed understanding of the non-linear physics of alpha heating and the complex impact of MeV-range fast ions on plasma dynamics becomes progressively more important. This paper provides a comprehensive overview of recent developments with the three-ion ICRF scenarios on Alcator C-Mod, ASDEX Upgrade and JET tokamaks. The results demonstrate the flexibility of these novel scenarios for heating bulk ions in D-T ≈ 50%-50% plasmas and efficient generation of MeV-range fast ions in multi-ion species plasmas. Several key results relevant for ITER and future fusion reactors are highlighted., This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 – EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor the European Commission can be held responsible for them. We thank the ITPA Energetic Particle Physics Topical Group for its support. Part of this work was also carried out in the framework of projects done for the ITER Scientist Fellow Network (ISFN). ITER is the Nuclear Facility INB No. 174. The views and opinions expressed herein do not necessarily reflect those of the ITER Organization. This publication is provided for scientific purposes only. Its contents should not be considered as commitments from the ITER Organization as a nuclear operator in the frame of the licensing process., Peer Reviewed, "Article signat per 78 autors/es: Ye. O. Kazakov; J. Ongena; M. Nocente; V. Bobkov; J. Garcia; V. G. Kiptily; M. Schneider; S. Wukitch; J. C. Wright; M. Dreval; K. K. Kirov; S. Mazzi; R. Ochoukov; S. E. Sharapov; Ž. Štancar; H. Weisen; Y. Baranov; M. Baruzzo; A. Bierwage; R. Bilato; A. Chomiczewska; R. Coelho; T. Craciunescu; K. Crombé; E. Delabie; E. de la Luna; R. Dumont; P. Dumortier; F. Durodié; J. Eriksson; M. Fitzgerald; J. Galdon-Quiroga; D. Gallart; M. Garcia-Munoz; L. Giacomelli; C. Giroud; J. Gonzalez-Martin; A. Hakola; R. Henriques; P. Jacquet; I. Jepu; T. Johnson; A. Kappatou; D. Keeling; D. King; C. Klepper; Ph. Lauber; M. Lennholm; E. Lerche; B. Lomanowski; C. Lowry; M. J. Mantsinen; M. Maslov; S. Menmuir; I. Monakhov; F. Nabais; M. F. F. Nave; C. Noble; E. Panontin; S. D. Pinches; A. R. Polevoi; D. Rigamonti; A. Sahlberg; M. Salewski; P. A. Schneider; H. Sheikh; K. Shinohara; P. Siren; S. Sumida; A. Thorman; R. A. Tinguely; D. Valcarcel; D. Van Eester; M. Van Schoor; J. Varje; M. Weiland; N. Wendler; JET Contributors, the ASDEX Upgrade Team and the EUROfusion MST1 Team", Postprint (author's final draft)

Objective.Proton therapy as the next generation radiation-based cancer therapy offers dominant advantages over conventional radiation therapy due to the utilization of the Bragg peak; however, range uncertainty in beam delivery substantially mitigates the advantages of proton therapy. This work reports using protoacoustic measurements to determine the location of proton Bragg peak deposition within a water phantom in real time during beam delivery.Approach.In protoacoustics, proton beams have a definitive range, depositing a majority of the dose at the Bragg peak; this dose is then converted to heat. The resulting thermoelastic expansion generates a 3D acoustic wave, which can be detected by acoustic detectors to localize the Bragg peak.Main results.Protoacoustic measurements were performed with a synchrocyclotron proton machine over the exhaustive energy range from 45.5 to 227.15 MeV in clinic. It was found that the amplitude of the acoustic waves is proportional to proton dose deposition, and therefore encodes dosimetric information. With the guidance of protoacoustics, each individual proton beam (7 pC/pulse) can be directly visualized with sub-millimeter (<0.7 mm) resolution using single beam pulse for the first time.Significance.The ability to localize the Bragg peak in real-time and obtain acoustic signals proportional to dose within tumors could enable precision proton therapy and hope to progress towardsin vivomeasurements.

To determine the safety of using argon as a deuteron beam stopping material, the  40Ar(d,p)41Ar cross section was measured at average deuteron energies of 3.6 MeV, 5.5 MeV, and 7.0 MeV using an activation method. A 16-MeV deuteron beam produced by Lawrence Berkeley National Laboratory's 88-Inch Cyclotron was degraded to each energy by nickel foils and the front wall of an aluminum gas chamber. The reduced-energy deuterons were used to activate a sample of natAr gas. After each irradiation, the gas chamber's  41Ar activation was measured with a high-purity germanium detector. The cross sections measured were larger than a previous measurement by ∼40%.

We have been developing a cyclotron accelerator for radioisotope production of medical use. The features of developed cyclotron system are compactness, light weight, and multi energy outputs. To achieve such features, coils are wound with rare-earth barium copper oxide (REBCO) tapes and the magnet has no iron core to generate an azimuthal varying field (AVF). To install the developed cyclotron accelerator into hospitals, an iron shield is needed for protection of leakage radiation and magnetic field. In this paper, to optimally design main coils with iron shield, a fast field computation method called Model Order Reduction (MOR) is adopted. Using MOR technique, the field computation is accelerated similar to 50 times. The error of MOR field computation is sufficiently small. Hence, the MOR is effective in the optimal configuration design of coils with iron shield. The optimized configuration of a miniaturized cyclotron accelerator magnet is also shown.

We have been developing a cyclotron accelerator for radioisotope production of medical use. The features of developed cyclotron system are compactness, light weight, and multi energy outputs. To achieve such features, coils are wound with rare-earth barium copper oxide (REBCO) tapes and the magnet has no iron core to generate an azimuthal varying field (AVF). To install the developed cyclotron accelerator into hospitals, an iron shield is needed for protection of leakage radiation and magnetic field. In this paper, to optimally design main coils with iron shield, a fast field computation method called Model Order Reduction (MOR) is adopted. Using MOR technique, the field computation is accelerated similar to 50 times. The error of MOR field computation is sufficiently small. Hence, the MOR is effective in the optimal configuration design of coils with iron shield. The optimized configuration of a miniaturized cyclotron accelerator magnet is also shown.

We have been developing a cyclotron accelerator for radioisotope production of medical use. The features of developed cyclotron system are compactness, light weight, and multi energy outputs. To achieve such features, coils are wound with rare-earth barium copper oxide (REBCO) tapes and the magnet has no iron core to generate an azimuthal varying field (AVF). To install the developed cyclotron accelerator into hospitals, an iron shield is needed for protection of leakage radiation and magnetic field. In this paper, to optimally design main coils with iron shield, a fast field computation method called Model Order Reduction (MOR) is adopted. Using MOR technique, the field computation is accelerated similar to 50 times. The error of MOR field computation is sufficiently small. Hence, the MOR is effective in the optimal configuration design of coils with iron shield. The optimized configuration of a miniaturized cyclotron accelerator magnet is also shown.

We have been developing a cyclotron accelerator for radioisotope production of medical use. The features of developed cyclotron system are compactness, light weight, and multi energy outputs. To achieve such features, coils are wound with rare-earth barium copper oxide (REBCO) tapes and the magnet has no iron core to generate an azimuthal varying field (AVF). To install the developed cyclotron accelerator into hospitals, an iron shield is needed for protection of leakage radiation and magnetic field. In this paper, to optimally design main coils with iron shield, a fast field computation method called Model Order Reduction (MOR) is adopted. Using MOR technique, the field computation is accelerated similar to 50 times. The error of MOR field computation is sufficiently small. Hence, the MOR is effective in the optimal configuration design of coils with iron shield. The optimized configuration of a miniaturized cyclotron accelerator magnet is also shown.

This article presents a very compact highly efficient solid-state power amplifier (SSPA) module at kilowatt level in a push-pull architecture. This SSPA is intended to be used as a modular RF source for a 20 kW cyclotron that operates in the low VHF band for radioisotopes production. For a compact design, a lumped LC balun is adopted instead of a traditional ferrite transformer for the 180° phase shift requirement of the push-pull architecture. Lumped harmonic traps are employed as harmonic tuning to achieve higher efficiency. This implementation enables an ultracompact design realized on a 90 mm X 70mm circuit board. Improved efficiency at reduced output power is achieved through a static supply voltage variation, which gives more than 90% efficiency over a 5 dB output power range. This approach enables considerable energy saving when applied to the whole cyclotron system. The achieved results show that the proposed SSPA with drain supply modulation is a very promising architecture for very high-power RF sources in cyclotrons for radioisotope production.

Identification of proteoforms, the different forms of a protein, is important to understand biological processes. A proteoform family is the set of different proteoforms from the same gene. We previously developed the software program Proteoform Suite, which constructs proteoform families and identifies proteoforms by intact-mass analysis. Here, we have applied this approach to top-down proteomic data acquired at the National High Magnetic Field Laboratory 21 tesla Fourier transform ion cyclotron resonance mass spectrometer (data available on the MassIVE platform with identifier MSV000085978). We explored the ability to construct proteoform families and identify proteoforms from the high mass accuracy data that this instrument provides for a complex cell lysate sample from the MCF-7 human breast cancer cell line. There were 2830 observed experimental proteforms, of which 932 were identified, 44 were ambiguous, and 1854 were unidentified. Of the 932 unique identified proteoforms, 766 were identified by top-down MS2 analysis at 1% false discovery rate (FDR) using TDPortal, and 166 were additional intact-mass identifications (∼4.7% calculated global FDR) made using Proteoform Suite. We recently published a proteoform level schema to represent ambiguity in proteoform identifications. We implemented this proteoform level classification in Proteoform Suite for intact-mass identifications, which enables users to determine the ambiguity levels and sources of ambiguity for each intact-mass proteoform identification.

Analysis of proteins and complexes under native mass spectrometric (MS) and solution conditions was typically performed using time-of-flight (ToF) analyzers, due to their routine high m/z transmission and detection capabilities. However, over recent years, the ability of Orbitrap-based mass spectrometers to transmit and detect a range of high molecular weight species is well documented. Herein, we describe how a 15 Tesla Fourier transform ion cyclotron resonance mass spectrometer (15 T FT-ICR MS) is more than capable of analyzing a wide range of ions in the high m/z scale (>5000), in both positive and negative instrument polarities, ranging from the inorganic cesium iodide salt clusters; a humanized IgG1k monoclonal antibody (mAb; 148.2 kDa); an IgG1-mertansine drug conjugate (148.5 kDa, drug-to-antibody ratio; DAR 2.26); an IgG1-siRNA conjugate (159.1 kDa; ribonucleic acid to antibody ratio; RAR 1); the membrane protein aquaporin-Z (97.2 kDa) liberated from a C8E4 detergent micelle; the empty MSP1D1-nanodisc (142.5 kDa) and the tetradecameric chaperone protein complex GroEL (806.2 kDa; GroEL dimer at 1.6 MDa). We also investigate different regions of the FT-ICR MS that impact ion transmission and desolvation. Finally, we demonstrate how the transmission of these species and resultant spectra are highly consistent with those previously generated on both quadrupole-ToF (Q-ToF) and Orbitrap instrumentation. This report serves as an impactful example of how FT-ICR mass analyzers are competitive to Q-ToFs and Orbitraps for high mass detection at high m/z.

One of the challenges that magnetic confinement fusion faces is achieving extreme temperatures inside the reactors. Absorption of electromagnetic waves in the ion cyclotron range of frequencies (ICRF) has demonstrated efficient plasma heating in present-day tokamak experiments and it is one of the three auxiliary heating methods foreseen for the International Thermonuclear Experimental Reactor (ITER). Therefore, the study of different heating schemes using ICRF waves is of utmost interest to optimize the fusion performance. The present thesis is focused in the computational assessment of plasma heating using ICRF waves and neutral beam injection (NBI) using the PION code. A strong emphasis is given to the physics behind these heating mechanisms and how they affect the fusion performance. This project has been carried out in the context of the present deuterium (D) campaign that is being performed at the Joint European Torus (JET) experimental reactor in preparation for the next deuterium-tritium (D-T) campaign DTE2, which is planned to begin in 2021. The results presented in this thesis consist of two parts. In the first part we model several D plasma discharges carried out at JET and we assess the role of different heating characteristics in the fusion yield in pure D plasmas. The second part of this project is focused on the extrapolation of a high performance plasma discharge to a 50%:50% D-T scenario. A comparison of the heating characteristics with pure D plasmas is provided, and special attention is given to the resulting fusion yield., Uno de los retos que afronta la fusión por confinamiento magnético es conseguir temperaturas extremas dentro de los reactores. La absorción de ondas electromagnéticas en el rango de frecuencias de ciclotrón de los iones (ICRF) ha demostrado ser un método eficiente para calentar el plasma en experimentos actuales de tokamaks. Por lo tanto, el estudio de diferentes esquemas de calentamiento con ondas ICRF es de especial relevancia para optimizar el rendimiento de la fusión. Este trabajo se centra en el análisis computacional del calentamiento del plasma con ondas ICRF y neutral beam injection (NBI) mediante el código PION. Se ha dado énfasis en la física detrás los mecanismos de calentamiento y cómo afectan al rendimiento de la fusión. Éste proyecto se ha llevado a cabo en el contexto de la presente campaña de plasmas de deuterio (D) en el reactor experimental Joint European Torus (JET) en preparación para la siguiente campaña de plasmas de deuterio-tritio (D-T), DTE2, prevista para 2021. Los resultados de éste trabajo se han presentado en dos partes. En la primera, se modelan varias descargas de plasma de D que han tenido lugar en JET y analizamos el rol del calentamiento en la potencia obtenida por fusión en plasmas de D. La segunda parte del proyecto consiste en la extrapolación de una descarga de alto rendimiento a un escenario de 50%:50% D-T, donde se compara el calentamiento con los plasmas de D y se analiza la potencia equivalente obtenida por fusión., Un dels reptes que afronta la fusió per confinament magnètic és aconseguir temperatures extremes dins dels reactors. L'absorció d'ones electromagnètiques en el rang de freqüències de ciclotró dels ions (ICRF) ha demostrat ser un mètode eficient per escalfar el plasma en experiments actuals de tokamaks. Per tant, l'estudi de diferents esquemes d'escalfament amb ones ICRF és d'especial rellevància per optimitzar el rendiment de la fusió. Aquest treball se centra en l'anàlisi computacional de l'escalfament del plasma amb ones ICRF i neutral beam injection (NBI) mitjançant el codi PION. S'ha donat èmfasi en la física darrere els mecanismes d'escalfament i com afecten el rendiment de la fusió. Aquest projecte s'ha dut a terme en el context de la present campanya de plasmes de deuteri (D) en el reactor experimental Joint European Torus (JET) en preparació per a la següent campanya de plasmes de deuteri-triti (D-T), DTE2, prevista per 2021. els resultats d'aquest treball s'han presentat en dues parts. En la primera, es modelen diverses descàrregues de plasma de D que han tingut lloc en JET i analitzem el paper de l'escalfament en la potència obtinguda per fusió en plasmes de D. La segona part de el projecte consisteix en l'extrapolació d'una descàrrega d'alt rendiment a un escenari de 50%: 50% D-T, on es compara l'escalfament amb els plasmes de D i s'analitza la potència equivalent obtinguda per fusió.

A new Center for Radiopharmaceutical Cancer Research was established at the Helmholtz-Zentrum Dresden-Rossendorf in order to centralize radionuclide production, radiopharmaceutical production and the chemical and biochemical research facilities. The newly installed cyclotron is equipped with two beamlines, two target selectors and several liquid, gas and solid target systems. The cyclotron including the target systems and first results of beam characterization measurements as well as results of the radionuclide production are presented. The produced radionuclides are automatically distributed from the targets to the destination hot cells. This process is supervised and controlled by an in-house developed system.

The TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional electron heating compatible with high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden its operational range without sacrificing its fundamental flexibility. The TCV program is rooted in a three-pronged approach aimed at ITER support, explorations towards DEMO, and fundamental research. A 1 MW, tangential neutral beam injector (NBI) was recently installed and promptly extended the TCV parameter range, with record ion temperatures and toroidal rotation velocities and measurable neutral-beam current drive. ITER-relevant scenario development has received particular attention, with strategies aimed at maximizing performance through optimized discharge trajectories to avoid MHD instabilities, such as peeling-ballooning and neoclassical tearing modes. Experiments on exhaust physics have focused particularly on detachment, a necessary step to a DEMO reactor, in a comprehensive set of conventional and advanced divertor concepts. The specific theoretical prediction of an enhanced radiation region between the two X-points in the low-field-side snowflake-minus configuration was experimentally confirmed. Fundamental investigations of the power decay length in the scrape-off layer (SOL) are progressing rapidly, again in widely varying configurations and in both D and He plasmas; in particular, the double decay length in L-mode limited plasmas was found to be replaced by a single length at high SOL resistivity. Experiments on disruption mitigation by massive gas injection and electron-cyclotron resonance heating (ECRH) have begun in earnest, in parallel with studies of runaway electron generation and control, in both stable and disruptive conditions; a quiescent runaway beam carrying the entire electrical current appears to develop in some cases. Developments in plasma control have benefited from pr, QC 20171212

The ITER project was created with the goal of showing the world that fusion energy is possible and can be a major step towards having a whole new kind of commercial reactors in the energy sector. Fusion energy is obtained from the fusion reactions that take place into a plasma that is at more than 150 million degrees Celsius, which is approximately 10 times the temperature at the core of the sun. How can such a high temperature be achieved? For the operation of the reactor, an external current is induced inside of the plasma. Up to more or less 1 keV (11.5 million degrees), the plasma has some resistivity, which means that there will be Ohmic heating due to that current owing through the plasma, that can be progressively increased. But after reaching 1 keV, the plasma resistivity becomes too low to keep heating it. This makes other external heating methods essential for the operation of the reactor. One of these external heating systems is the Electron Cyclotron Resonance Heating (ECRH). It consists in heating the electrons inside the plasma by means of electromagnetic waves at the resonance frequency of a given surface in the magnetic eld. This radio frequency is generated in a device called Gyrotron. In this device, electrons are emitted from an 'electron gun' and are accelerated through a tube. These electrons oscillate in the presence of an external magnetic eld, generating the electromagnetic wave that, after being adapted, will be guided inside the reactor. The Gyrotron needs several auxiliary systems to operate such as power supplies, superconducting magnets and ion pumps. They have to work correctly and in the right moment, coordinated with the whole plant operation. The Electron Cyclotron Control System (or ECCS) is in charge of controlling the 24 Gyrotrons of the ITER reactor, together with the high voltage power supplies, the transmission lines and the launchers. The ECCS ensures the correct operation of the whole system and its protection. This project w

Purpose: In this work, ion recombination is studied as a function of energy and depth in carbon ion beams. Methods: Measurements were performed in three different passively scattered carbon ion beams with energies of 62 MeV/n, 135 MeV/n, and 290 MeV/n using various types of plane-parallel ionization chambers. Experimental results were compared with two analytical models for initial recombination. One model is generally used for photon beams and the other model, developed by Jaffe, takes into account the ionization density along the ion track. An investigation was carried out to ascertain the effect on the ion recombination correction with varying ionization chamber orientation with respect to the direction of the ion tracks. The variation of the ion recombination correction factors as a function of depth was studied for a Markus ionization chamber in the 62 MeV/n nonmodulated carbon ion beam. This variation can be related to the depth distribution of linear energy transfer. Results: Results show that the theory for photon beams is not applicable to carbon ion beams. On the other hand, by optimizing the value of the ionization density and the initial mean-square radius, good agreement is found between Jaffes theory and the experimental results. As predicted by Jaffes theory, the results confirm that ion recombination corrections strongly decrease with an increasing angle between the ion tracks and the electric field lines. For the Markus ionization chamber, the variation of the ion recombination correction factor with depth was modeled adequately by a sigmoid function, which is approximately constant in the plateau and strongly increasing in the Bragg peak region to values of up to 1.06. Except in the distal edge region, all experimental results are accurately described by Jaffes theory. Conclusions: Experimental results confirm that ion recombination in the investigated carbon ion beams is dominated by initial recombination. Ion recombination corrections are found t

Heating with ICRF waves is a well-established method on present-day tokamaks and one of the heating systems foreseen for ITER. However, further work is still needed to test and optimize its performance in fusion devices with metallic high-Z plasma facing components (PFCs) in preparation of ITER and DEMO operation. This is of particular importance for the bulk ion heating capabilities of ICRF waves. Efficient bulk ion heating with the standard ITER ICRF scheme, i.e. the second harmonic heating of tritium with or without 3He minority, was demonstrated in experiments carried out in deuterium-tritium plasmas on JET and TFTR and is confirmed by ICRF modelling. This paper focuses on recent experiments with 3He minority heating for bulk ion heating on the ASDEX Upgrade (AUG) tokamak with ITER-relevant all-tungsten PFCs. An increase of 80% in the central ion temperature Ti from 3 to 5.5 keV was achieved when 3 MW of ICRF power tuned to the central 3He ion cyclotron resonance was added to 4.5 MW of deuterium NBI. The radial gradient of the Ti profile reached locally values up to about 50 keV/m and the normalized logarithmic ion temperature gradients R/LTi of about 20, which are unusually large for AUG plasmas. The large changes in the Ti profiles were accompanied by significant changes in measured plasma toroidal rotation, plasma impurity profiles and MHD activity, which indicate concomitant changes in plasma properties with the application of ICRF waves. When the 3He concentration was increased above the optimum range for bulk ion heating, a weaker peaking of the ion temperature profile was observed, in line with theoretical expectations., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission., Peer Reviewed, Postprint (published version)

We carried out global Particle-in-Cell simulations of the interaction between the solar wind and a magnetosphere to study the kinetic collisionless physics in super-critical quasi-perpendicular shocks. After an initial simulation transient, a collisionless bow shock forms as a result of the interaction of the solar wind and a planet magnetic dipole. The shock ramp has a thickness of approximately one ion skin depth and is followed by a trailing wave train in the shock downstream. At the downstream edge of the bow shock, whistler waves propagate along the magnetic field lines and the presence of electron cyclotron waves has been identified. A small part of the solar wind ion population is specularly reflected by the shock while a larger part is deflected and heated by the shock. Solar wind ions and electrons are heated in the perpendicular directions. Ions are accelerated in the perpendicular direction in the trailing wave train region. This work is an initial effort to study the electron and ion kinetic effects developed near the bow shock in a realistic magnetic field configuration., QC 20151130

Ion cyclotron resonance frequency heating (ICRH) is one of the most important mechanisms to heat fusion plasma. The magnetic field generated by the magnetic coils forces ions to follow a cyclotron trajectory around the magnetic field lines due to the Lorentz force. Therefore, ions revolve around the magnetic field lines in a determined frequency, the so called ion cyclotron frequency. ICRH is based on launching electromagnetic waves from the low-field side in such a way that their frequency matches the one from ions cyclotron frequency. When both frequencies match, another effect begins to occur, the wave-particle interaction. At this point, ions start damping the wave by absorbing its energy. This effect modifies the distribution function of ions which develops a tail in the high energy region. The fast ions produced by the energy absorption from the electromagnetic waves play an important role in heating the bulk plasma. Therefore, it is crucial to know how the energy of the wave is distributed among ions and electrons, and how the fast ions produced deliver their energy to the other particles, ions and electrons. This Msc thesis is a first computational assessment of bulk plasma heating for DEMO. The DEMOnstration power plant is a proposed nuclear fusion power plant that is expected to be built after the experimental reactor ITER. It will be the first fusion reactor to produce electrical energy. Its parameters and scope are still not fixed yet, a few different yet similar designs exist. However, the physical dimensions and energy output in DEMO are much bigger than that of ITER. In fact, DEMO’s 2 to 4 gigawatts of fusion power will be in the scale of the modern electric power plants. In this sense, the analysis here presented, takes into account the evolution of the fast ions and assesses their behavior at DEMO. The ICRH scenarios studied are the second harmonic tritium with and without 3He in D-T plasma as they are regarded as the most promising ICRH scenarios.

Ion cyclotron resonance frequency heating (ICRF) is one of the auxiliary heating schemes presently envisaged for ITER and DEMO. In this paper we analyse the potential of ICRF waves to heat the fuel ions in DEMO. Our analysis is carried out for the EU DEMO design¹ (B = 6.8 T, I = 18.6 MA, R = 9.25 m, a = 2.64 m) optimized for a maximum pulse length of 2.3 hrs using the ICRF modelling codes PION and TORIC [2, 3] . We focus on second harmonic heating for tritium and fundamental minority heating of ³He with a few percent of ³He in a 50%:50% D-T plasma. The dependence of the ICRF characteristics and the ICRF-accelerated ions on the ICRF and plasma parameters is investigated, giving special attention to the DEMO design point at a plasma temperature of 30 keV and an electron density of 1.2 · 10²⁰ m⁻ ³.

Ion cyclotron resonance frequency (ICRF) heating is one of the auxiliary heating schemes presently envisaged for ITER and DEMO. In this paper we analyse the potential of ICRF waves to heat the fuel ions in DEMO. Our analysis is carried out for the DEMO1 Reference Scenario from October 2013 (B = 6.8 T, I = 18.6 MA, R = 9.25 m, a = 2.64 m) optimized for a maximum pulse length of 2.3 hrs using the ICRF modelling codes PION and TORIC. We focus on second harmonic heating of tritium and fundamental minority heating of 3He ions (with a few percent of 3He) in a 50%:50% D-T plasma. The dependence of the ICRF characteristics and the ICRF-accelerated ions on the ICRF and plasma parameters is investigated, giving special attention to the DEMO design point at a core plasma temperature of 30 keV and an electron density of 1.2·1020 m−3., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. We are grateful to Dr. R. Wenninger and Dipl.-Ing T. Franke (PPPT, Garching) for DEMO parameters. They are for the DEMO1 Reference Scenario from October 2013 optimised for a maximum pulse length of 2.3 hrs (with CD 2.7hrs), Peer Reviewed, Postprint (published version)

Third harmonic cyclotron heating is an effective tool for accelerating deuterium (D) beams to the MeV energy range, suitable for studying ITER relevant fast particle physics in plasmas without significant tritium content. Such experiments were recently conducted in JET with an ITER like wall in D plasmas with 3He concentrations up to 30% in order to boost the fusion reactivity by D-3He reactions. The harmonic cyclotron heating produces high-energy tails in the MeV range of D ions by on-axis heating and of 3He ions by tangential off-axis heating. The discharges are characterized by long sawtooth free periods and a rich spectrum of MHD modes excited by the fast D and 3He ions. The partitions of the power, which depend on the distribution function of D, vary strongly over several slowing down times. Self-consistent modelling of the distribution function with the SELFO-light code are presented and compared with experimental data from fast particle diagnostics., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission., Peer Reviewed, Postprint (published version)

Heating with ICRF waves is a well-established method on present-day tokamaks and one of the heating systems foreseen for ITER. However, further work is still needed to test and optimize its performance in fusion devices with metallic high-Z plasma facing components (PFCs) in preparation of ITER and DEMO operation. This is of particular importance for the bulk ion heating capabilities of ICRF waves. Efficient bulk ion heating with the standard ITER ICRF scheme, i.e. the second harmonic heating of tritium with or without 3He minority, was demonstrated in experiments carried out in deuterium-tritium plasmas on JET and TFTR and is confirmed by ICRF modelling. This paper focuses on recent experiments with 3He minority heating for bulk ion heating on the ASDEX Upgrade (AUG) tokamak with ITER-relevant all-tungsten PFCs. An increase of 80% in the central ion temperature Ti from 3 to 5.5 keV was achieved when 3 MW of ICRF power tuned to the central 3He ion cyclotron resonance was added to 4.5 MW of deuterium NBI. The radial gradient of the Ti profile reached locally values up to about 50 keV/m and the normalized logarithmic ion temperature gradients R/LTi of about 20, which are unusually large for AUG plasmas. The large changes in the Ti profiles were accompanied by significant changes in measured plasma toroidal rotation, plasma impurity profiles and MHD activity, which indicate concomitant changes in plasma properties with the application of ICRF waves. When the 3He concentration was increased above the optimum range for bulk ion heating, a weaker peaking of the ion temperature profile was observed, in line with theoretical expectations., This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission., Peer Reviewed, Postprint (published version)

This thesis reports results of MCNP-5 calculations, with the nuclear data library FENDL-2.1, to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) antenna in the blanket of a DEMO fusion power reactor. Apart from a representative final configuration of both the antenna and the DEMO reactor, a parametric analysis is done on the parameters which most strongly affect the TBR. These are the type of breeding blanket (Helium Cooled Pebble Bed, Helium Cooled Lithium Lead and Water Cooled Lithium Lead), the covering ratio of the straps of the antenna (0.49, 0.72 and 0.94), the depth of the antenna (20 cm and 40 cm), the thickness of the straps (2 cm, 4 cm and a double layer of 0.2 cm plus 2.5 cm with the composition of the First Wall), and finally the poloidal position of the antenna (0º, which is the equatorial port, 40º and 90º, which is the upper port). For an antenna with a full toroidal circumference of 360º, located poloidally at 40º with a poloidal extension of 1 m and a total First Wall surface of 67 m2, the reduction of the TBR is 0.35% for a HCPB blanket concept, 0.53% for a HCLL blanket concept and 0.51% for a WCLL blanket concept. In all cases, including the parametric analysis, the loss of TBR remains below 0.61%, and the antenna is thus shown to have only a marginal effect on the TBR for a DEMO reactor.

Fourier transform ion cyclotron resonance mass spectrometry (FTICR MS) delivers high resolving power, mass measurement accuracy, and the capabilities for unambiguously sequencing by a top-down MS approach. Here, we report isotopic resolution of a 158 kDa protein complex, tetrameric aldolase with an average absolute deviation of 0.36 ppm and an average resolving power of ~520 000 at m/z 6033 for the 26+ charge state in magnitude mode. Phase correction further improves the resolving power and average absolute deviation by 1.3-fold. Furthermore, native top-down electron capture dissociation (ECD) enables the sequencing of 168 C-terminal amino acid (AA) residues out of 463 total AAs. Combining the data from top-down MS of native and denatured aldolase complexes, a total of 56% of the total backbone bonds were cleaved. The observation of complementary product ion pairs confirms the correctness of the sequence and also the accuracy of the mass fitting of the isotopic distribution of the aldolase tetramer. Top-down MS of the native protein provides complementary sequence information to top-down ECD and collisonally activated dissociation (CAD) MS of the denatured protein. Moreover, native top-down ECD of aldolase tetramer reveals that ECD fragmentation is not limited only to the flexible regions of protein complexes and that regions located on the surface topology are prone to ECD cleavage.

Electron cyclotron waves are widely used in magnetic confinement devices, specially in those involved in nuclear fusion research, to heat the electrons and achieve the ignition temperature. A still unsolved issue is the determination of the exact position where the cyclotron power is absorbed by the plasma. Although a verified theoretical method exists to determine the absorbed zone, it relies on local and integral density and temperature values, quantities that are not known with sufficient precision. The basics of a technique that allow determining the cyclotron power deposition profile independently have been developed in this thesis, which is applicable to recent and historical FTU tokamak data and can be used as a reliable real-time closed-loop control system of MHD instabilities in future tokamaks.

Spokes are azimuthally propagating perturbations in the plasma discharge of Hall Effect Thrusters (HETs) that travel in the E x B direction and have been observed in many different systems. The propagation of azimuthal spokes are investigated in a 6 kW HET known as the H6 using ultra-fast imaging and azimuthally spaced probes. A spoke surface is a 2-D plot of azimuthal light intensity evolution over time calculated from 87,500 frames/s videos. The spoke velocity has been determined using three methods with similar results: manual fitting of diagonal lines on the spoke surface, linear cross-correlation between azimuthal locations and an approximated dispersion relation. The spoke velocity for three discharge voltages (300, 400 and 450 V) and three anode mass flow rates (14.7, 19.5 and 25.2 mg/s) yielded spoke velocities between 1500 and 2200 m/s across a range of normalized magnetic field settings. The spoke velocity was inversely dependent on magnetic field strength for low B-field settings and asymptoted at B-field higher values. The velocities and frequencies are compared to standard drifts and plasma waves such as E x B drift, electrostatic ion cyclotron, magnetosonic and various drift waves. The empirically approximated dispersion relation yielded a characteristic velocity that matched the ion acoustic speed for 5 eV electrons that exist in the near-anode and near-field plume regions of the discharge channel based on internal measurements. Thruster performance has been linked to operating mode where thrust-to-power is maximized when azimuthal spokes are present so investigating the underlying mechanism of spokes will benefit thruster operation., The original document contains color images. Presented at the 33rd International Electric Propulsion Conference, The George Washington University, Washington, D.C., USA October 6 10, 2013

The Massachusetts Institute of Technology undertook to design, fabricate and test a prototype compact superconducting proton cyclotron which addressed all fundamental design and performance issues for a cyclotron at a final energy of 250 MeV and final beam intensity of 1 mA with less than 0.1% extraction loss. In March 2012, DTRA suspended work on the project indefinitely. This report documents the accomplishments and status of work on the five major subsystems of the project: 1) proton injection using external electron cyclotron resonance source with axial injection using spiral inflector; 2) magnetic field design; 3) radio frequency accelerating cavities; 4) cryogenic system; 5)beam extraction., Prepared by MIT under contract with Pennsylvania State University/ Applied Research Laboratory with funding from the Defense Threat Reduction Agency.

This thesis consists of two parts. The first part considers the e effect of microwave radiation on magnetotransport in high quality GaAs/AlGaAs heterostructure two dimensional electron systems. The effect of microwave (MW) radiation on electron temperature was studied by investigating the amplitude of the Shubnikov de Haas (SdH) oscillations in a regime where the cyclotron frequency omegaC and the MW angular frequency satisfy 2omega= omegac = 3:5omega. The results indicate negligible electron heating under modest MW photoexcitation, in agree ment with theoretical predictions. Next, the effect of the polarization direction of the linearly polarized MWs on the MW induced magnetoresistance oscillation amplitude was investigated. The results demonstrate the first indications of polarization dependence of MW induced magnetoresistance oscillations. In the second part, experiments on the magnetotransport of three dimensional highly oriented pyrolytic graphite (HOPG) reveal a non-zero Berry phase for HOPG. Furthermore, a novel phase relation between oscillatory magneto and Hall- resistances was discovered from the studies of the HOPG specimen.

A novel method for efficient analysis of ion beam acceleration in an isochronous cyclotron is proposed. Numerical simulation is used to perform multiple beam dynamics analyses on the conveniently chosen subsets of data; consequently, the total quantity of studied data is significantly reduced. The obtained results provide direct insight into beam behavior and quality of acceleration. Therefore, the analysis is not only efficient, but detailed and systematic as well. It is used to assess the impact of the accelerated orbit optimization to the enhancement of acceleration efficiency when study is extended from a single test ion to the complete ion beam consideration.

Accelerated ion beams are often extracted from a cyclotron by stripping some of ions electrons at the end of the acceleration process. Stripping extraction system is commonly designed and optimized using computer simulations of beam dynamics at a later stage of a cyclotron project. However, minor changes in the distance between the magnet poles are proven to cause large displacements of the optimal position of high-energy transport line. It is shown that simple analytical formulas give good prediction of the position and direction of beam exit after stripping extraction and are useful tool for preliminary facility layout planning.

Systematic errors caused by the deficiencies of the measurement equipment are occurring relatively often in the engineering practice. The magnetic field measurement system of the VINCY Cyclotron has been designed well; however, due to the practical limitations in the machining process fabrication errors are imminent. We present our experiences with the produced measurement system and the techniques used for the detection and correction of errors. A change in the measuring protocol is suggested in order to overcome otherwise unavoidable errors caused by measuring system machining imperfections. (C) 2012 Elsevier B.V. All rights reserved.

Systematic errors caused by the deficiencies of the measurement equipment are occurring relatively often in the engineering practice. The magnetic field measurement system of the VINCY Cyclotron has been designed well; however, due to the practical limitations in the machining process fabrication errors are imminent. We present our experiences with the produced measurement system and the techniques used for the detection and correction of errors. A change in the measuring protocol is suggested in order to overcome otherwise unavoidable errors caused by measuring system machining imperfections. (C) 2012 Elsevier B.V. All rights reserved.

Accelerated ion beams are often extracted from a cyclotron by stripping some of ions electrons at the end of the acceleration process. Stripping extraction system is commonly designed and optimized using computer simulations of beam dynamics at a later stage of a cyclotron project. However, minor changes in the distance between the magnet poles are proven to cause large displacements of the optimal position of high-energy transport line. It is shown that simple analytical formulas give good prediction of the position and direction of beam exit after stripping extraction and are useful tool for preliminary facility layout planning.

A novel method for efficient analysis of ion beam acceleration in an isochronous cyclotron is proposed. Numerical simulation is used to perform multiple beam dynamics analyses on the conveniently chosen subsets of data; consequently, the total quantity of studied data is significantly reduced. The obtained results provide direct insight into beam behavior and quality of acceleration. Therefore, the analysis is not only efficient, but detailed and systematic as well. It is used to assess the impact of the accelerated orbit optimization to the enhancement of acceleration efficiency when study is extended from a single test ion to the complete ion beam consideration.

Current-driven electrostatic ion-cyclotron instability has so far been studied for Maxwellian plasma with isotropic and anisotropic temperatures. Since satellite-measured particle velocity distributions in space are often better modeled by the generalized Lorentzian (kappa) distributions and since temperature anisotropy is quite common in space plasmas, theoretical analysis of the current-driven, electrostatic ion-cyclotron instability is carried out in this paper for electron-proton plasma with anisotropic temperatures, where the particle parallel velocity distributions are modeled by kappa distributions and the perpendicular velocity distributions are modeled by Maxwellian distributions. Stability properties of the excited ion cyclotron modes and, in particular, their dependence on electron to ion temperature ratio and ion temperature anisotropy are presented in more detail. For comparison, the corresponding results for bi-Maxwellian plasma are also presented. Although the stability properties of the ion cyclotron modes in the two types of plasmas are qualitatively similar, significant quantitative differences can arise depending on the values of ke and ki. The comparative study is based on the numerical solutions of the respective linear dispersion relations. Quasilinear estimates of the resonant ion heating rates due to ion-cyclotron turbulence in the two types of plasma are also presented for comparison, Published in Physics of Plasmas, v18 p092106(1)-092106(12), 2011.

The neutron source at the Indiana University Cyclotron Facility produces neutrons via proton bombardment of a natural beryllium (100% 9Be) target. This source has two beam lines: the LENS and the NREP. The energy spectrum of the neutrons produced on the NREP beam line has not yet been characterized. Through simulation using the GEANT and MCNP particle transport codes as well as neutron activation analysis experiments, an attempt was made to characterize the energy spectrum of the neutron production source. First, the neutron production spectrum of beryllium, simulated using GEANT, was compared with literature; there are significant deviations. Next, foils and wires of pure elements were irradiated in the neutron beam target area and the resulting gamma spectrum measured. This information was used in an unfolding code, SAND-II, to deconvolve the neutron energy spectrum observed at the target. A number of approximations were made to properly account for beam duty time and neutron production anisotropy. The resultants provide a better understanding of the spectrum, but continued work is needed to produce a useful spectrum for the users of the facility., The original document contains color images.

This report describes the first calibration of the Compact Environmental Anomaly Sensor (CEASE) instrument particle telescope with high energy (>20 MeV) protons. The two units calibrated were S/N 004 (flight unit w/tungsten collimator) and S/N 006 (engineering unit identical to the Tri-Service Experiment 5 [TSX-5]) CEASE. Both instruments were calibrated at the cyclotron at the Francis H. Burr Proton Therapy Center at the Massachusetts General Hospital (MGH). We report the results of those calibrations and the subsequent analyses.

The stripping extraction system of a cyclotron is prized by the range and quality of beams it delivers. The gap size of a cyclotron magnet is one of the parameters which significantly influence the design as well as the output characteristics of the stripping extraction system. The vertical dimension of the beam as well as of the extraction system elements placed inside a vacuum chamber is limited by the magnet gap size. Beside this direct influence, the indirect effect of the magnet gap size on stripping extraction occurs through the magnetic field and its impact on the beam dynamics in the extraction region. The performance of the extraction system is optimized by the proper placement of the point of beam exit from the cyclotron. It is shown that the optimal position of the exit point strongly depends on the magnet gap size. The performance of the optimized stripping extraction system for a smaller gap size is found to be somewhat better.

¿Es posible acelerar una bola mediante la generación de campos magnéticos? Este proyecto tiene como objetivo diseñar e implementar una maqueta que permita acelerar una bola metálica en un circuito cerrado, inspirado en un ciclotrón. La bola metálica debe acelerarse dentro de un circuito cerrado a partir de buscar disparos óptimos en una bobina. Los disparos se buscarán en función de la velocidad de la bola y de la distancia de esta respecto la bobina. Para simular el sistema utilizamos el programa SIMULINK de MATLAB a partir de las ecuaciones diferencias del sistema y utilizando la función fminsearh para encontrar los disparos óptimos. En las simulaciones comprobamos que era posible encontrar puntos de disparo y acelerar la bola mediante campos magnéticos producidos por un grupo de bobinas. Para llevar esto a la práctica se ha realizado el montaje de una maqueta basándonos en el modelo de un ciclotrón. Decidimos utilizar las bobinas más pequeñas que nos permitieran mover la bola y de esa manera maximizar la importancia de la obtención de los puntos de disparo óptimos. Para implementar el control y probar las simulaciones realizadas decidimos utilizar una placa FLEX que el departamento disponía en ese momento. Esta placa incluye un microprocesador DSPIC con un Kernel en tiempo real. Una vez construida la maqueta y realizada su puesta en marcha más programación del control en la placa FLEX se han determinado los puntos de disparo óptimos y se han obtenido resultados prácticos que confirman las simulaciones realizadas en el inicio del proyecto.

The stripping extraction system of a cyclotron is prized by the range and quality of beams it delivers. The gap size of a cyclotron magnet is one of the parameters which significantly influence the design as well as the output characteristics of the stripping extraction system. The vertical dimension of the beam as well as of the extraction system elements placed inside a vacuum chamber is limited by the magnet gap size. Beside this direct influence, the indirect effect of the magnet gap size on stripping extraction occurs through the magnetic field and its impact on the beam dynamics in the extraction region. The performance of the extraction system is optimized by the proper placement of the point of beam exit from the cyclotron. It is shown that the optimal position of the exit point strongly depends on the magnet gap size. The performance of the optimized stripping extraction system for a smaller gap size is found to be somewhat better.

Based on theoretical calculations, the Auger emitter 58mCo has been identified as a potent nuclide for targeted radionuclide therapy of small tumors. During the production of this isotope, the coproduction of the long-lived ground state 58gCo is unfortunately unavoidable, as is ingrowth of the ground state following the isomeric decay of 58mCo. The impact of 58gCo as a bþ- and c-emitting impurity should be included in the dosimetric analysis. The purpose of this study was to investigate this critical part of dosimetry based on experimentally determined production yields of 58mCo and 58gCo using a low-energy cyclotron. Also, the cellular S-values for 58mCo have been calculated and are presented here for the first time.

Reaction cross sections for stable nuclei at intermediate energies have been measured precisely and systematically. The data have been found to be reproduced nicely by the optical‐limit approximation of Glauber theory modified to include the nucleon multiple scattering effect and the Fermi‐motion effect. Applying this prescription, the nucleon density distribution of 17Ne has been studied. The surface structure of 8B and 11Be has been also studied using this prescription and hydrogen targets. Using the RIBF that has just started application to studies of exotic nuclei, neutron‐rich Ne isotopes around the Island of Inversion have been investigated through measurements of their interaction cross sections.

A high-performance liquid chromatography-high resolution Fourier transform ion cyclotron resonance mass spectrometry (HPLC-FTICR-MS) method was developed to investigate the metabolism of ginsenosides in in vitro models of the gastro-intestinal tract. The metabolites were identified by high-resolution tandem mass spectrometry. Degradation and bioconversion routes of the different ginsenosides at acidic (gastric) conditions and in the presence of intestinal microbiota were elaborated. Besides hydrolysis (deglycosylation) also hydration reactions occurred at acidic conditions. The results illustrate the value of metabolite profiling by HPLC-FTICR-MS for understanding of the mechanisms in bioavailability of herbal drugs and their metabolites. © 2008 Elsevier B.V. All rights reserved.