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Funding Information: This work is supported by US DOE Contracts DE-SC0020337, DE-AC05-00OR22725, DE-FC02-04ER54698, DE-AC02-09CH11466 and DE-SC0015878. This research used resources of the National Energy Research Scientific Computing Center (NERSC), a US Department of Energy Office of Science User Facility located at Lawrence Berkeley National Laboratory, operated under Contract No. DE-AC02-05CH11231 using NERSC Award FES-ERCAP20598. The ASCOT5 project was partially funded by the Academy of Finland Project Nos. 324759 and 298126. The ASCOT5 project has received funding from the European Research Council under Grant Agreement No. 647121. This ASCOT5 project has been carried out within the framework of the EUROfusion consortium and has received funding from the Euratom Research and Training Programme under Grant Agreement No. 633053. X. Wang’s 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). The views and opinions expressed herein do not necessarily reflect those of the European Commission. | openaire: EC/H2020/647121/EU//PLASMA | openaire: EC/H2020/633053/EU//EUROfusion An imaging neutral particle analyzer (INPA) provides energy and radially resolved measurements of the confined fast-ion population ranging from the high-field side to the edge on the midplane of the DIII-D tokamak. In recent experiments, it was used to diagnose fast-ion flow in the INPA-interrogated phase-space driven by multiple, marginally unstable Alfvén eigenmodes (AEs). The key features of this measured fast-ion flow are: (I) a fast-ion flow from q min and the injection energy (81 keV) towards lower energies and plasma periphery.(II) A flow from the same location towards higher energies and the plasma core, (III) a phase-space 'hole' at the injected energy and plasma core and (IV) a pile-up at the plasma core at lower energies ( 1/460 keV). Ad hoc energetic particle diffusivity modelling of TRANSP significantly deviates from the observation. Comparably, a reduced modelling, i.e. a combination of NOVA-K and ASCOT5 code with the measured mode structure and amplitude, generally reproduce some key features of the observed phase-space flow, but largely failed to interpret fast ion depletion near the plasma axis. At last, self-consistent, first-principle multi-phase hybrid simulations that include realistic neutral beam injection and collisions are able to reproduce most features of the time-resolved phase-space flow. During consecutive hybrid phases, an RSAE consistent with the experiment grows and saturates, redistributing the injected fast ions. The resulting synthetic INPA images are in good agreement with the measurement near the injection energy. The simulations track the fast-ion redistribution within the INPA range, confirming that the measured fast-ion flow follows streamlines defined by the intersection of phase-space surfaces of constant magnetic moment μ and constant E′ = nE + ωP φ, where n and ω are the instability toroidal mode number and frequency, and E and P φ the ion energy and toroidal canonical momentum. Nonperturbative effects are required to reproduce the depletion of fast ions near the magnetic axis at the injection energy.

The operation of a 3D coil—passively driven by the current quench (CQ) loop voltage—for the deconfinement of runaway electrons (REs) is modeled for disruption scenarios in the SPARC and DIII-D tokamaks. Nonlinear magnetohydrodynamic (MHD) modeling is carried out with the NIMROD code including time-dependent magnetic field boundary conditions to simulate the effect of the coil. Further modeling in some cases uses the ASCOT5 code to calculate advection and diffusion coefficients for REs based on the NIMROD-calculated fields, and the DREAM code to compute the runaway evolution in the presence of these transport coefficients. Compared with similar modeling in Tinguely et al (2021 Nucl. Fusion 61 124003), considerably more conservative assumptions are made with the ASCOT5 results, zeroing low levels of transport, particularly in regions in which closed flux surfaces have reformed. Of three coil geometries considered in SPARC, only the n = 1 coil is found to have sufficient resonant components to suppress the runaway current growth. Without the new conservative transport assumptions, full suppression of the RE current is maintained when the thermal quench MHD is included in the simulation or when the RE current is limited to 250kA, but when transport in closed flux regions is fully suppressed, these scenarios allow RE beams on the order of 1–2 MA to appear. Additional modeling is performed to consider the effects of the close ideal wall. In DIII-D, the CQ is modeled for both limited and diverted equilibrium shapes. In the limited shape, the onset of stochasticity is found to be insensitive to the coil current amplitude and governed largely by the evolution of the safety-factor profile. In both devices, prediction of the q-profile evolution is seen to be critical to predicting the later time effects of the coil.

Alarge superconducting machine, JT-60SA has been constructed to provide major contributions to the ITER program and DEMO design. For the success of the ITER project and fusion reactor, understanding and development of plasma controllability in ITER and DEMO relevant higher beta regimes are essential. JT-60SA has focused the program on the plasma controllability for scenario development and risk mitigation in ITER as well as on investigating DEMO relevant regimes. This paper summarizes the high research priorities and strategy for the JT-60SA project. Recent works on simulation studies to prepare the plasma physics and control experiments are presented, such as plasma breakdown and equilibrium controls, hybrid and steady-state scenario development, and risk mitigation techniques. Contributions of JT-60SA to ITER and DEMOhave been clarified through those studies. Peer Reviewed Article escrit per 127 autors/autores: M Yoshida, G Giruzzi, N Aiba, J F Artaud, J Ayllon-Guerola, L Balbinot, OBeeke, E Belonohy, P Bettini, W Bin, A Bierwage, T Bolzonella, M Bonotto, CBoulbe, J Buermans, M Chernyshova, S Coda, R Coelho, S Davis, C Day, GDeTommasi, M Dibon, A Ejiri, G Falchetto, A Fassina, B Faugeras, L Figini, M Fukumoto, S Futatani, K Galazka, J Garcia, M Garcia-Muñoz, L Garzotti, L Giacomelli, L Giudicotti, S Hall, N Hayashi, C Hoa, M Honda, K Hoshino, M Iafrati, A Iantchenko, S Ide, S Iio, R Imazawa, S Inoue, A Isayama, E Joffrin, K Kamiya, Y Ko, M Kobayashi, T Kobayashi, G Kocsis, A Kovacsik, T Kurki-Suonio, B Lacroix, P Lang, Ph Lauber, A Louzguiti, E de la Luna, G Marchiori, M Mattei, A Matsuyama, S Mazzi, A Mele, F Michel, Y Miyata, J Morales, P Moreau, A Moro, T Nakano, M Nakata, E Narita, R Neu, S Nicollet, M Nocente, S Nowak, F P Orsitto, V Ostuni, Y Ohtani, N Oyama, R Pasqualotto, B Pégourié, E Perelli, L Pigatto, C Piccinni, A Pironti, P Platania, B Ploeckl, D Ricci, P Roussel, G Rubino, R Sano, K Särkimäki, K Shinohara, S Soare, C Sozzi, S Sumida, T Suzuki, Y Suzuki, T Szabolics, T Szepesi, Y Takase, M Takech, N Tamura, K Tanaka, H Tanaka, M Tardocchi, A Terakado, H Tojo, T Tokuzawa, A Torre, N Tsujii, H Tsutsui, Y Ueda, H Urano, M Valisa, M Vallar, J Vega, F Villone, T Wakatsuki, T Wauters, M Wischmeier, S Yamoto, L Zani

In Izzo et al (2022 Nucl. Fusion 62 096029), state-of-the-art modeling of thermal and current quench (CQ) magnetohydrodynamics (MHD) coupled with a self-consistent evolution of runaway electron (RE) generation and transport showed that a non-axisymmetric (n = 1) in-vessel coil could passively prevent RE beam formation during disruptions in SPARC, a compact high-field tokamak projected to achieve a fusion gain Q > 2 in DT plasmas. However, such suppression requires finite transport of REs within magnetic islands and re-healed flux surfaces; conservatively assuming zero transport in these regions leads to an upper bound of RE current ∼ 1 M A compared to ∼ 8.7 M A of pre-disruption plasma current. Further investigation finds that core-localized electrons, within r / a < 0.3 and with kinetic energies ∼ 0.2 – 15 M e V , contribute most to the RE plateau formation. Yet only a relatively small amount of transport, i.e. a diffusion coefficient ∼ 18 m 2 s − 1 , is needed in the core to fully mitigate these REs. Properly accounting for (a) the CQ electric field’s effect on RE transport in islands and (b) the contribution of significant RE currents to disruption MHD may help achieve this.

openaire: EC/H2020/633053/EU//EUROfusion Funding Information: The author (X. D. Du) would like to thank M. Podestà, G. J. Kramer, and R.Nazikian for fruitful discussions. This work was supported by the US DOE under DE-AC05-00OR22725, DE-FC02-04ER54698, DE-AC02-09CH11466, and DE-SC0015878. The ASCOT5 project has received funding from the European Research Council under Grant Agreement No. 647121. This ASCOT5 project has been carried out within the framework of the EUROfusion consortium and has received funding from the Euratom research and training programme under grant agreement No 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. The ASCOT5 project was also partially funded by the Academy of Finland projects No. 324759 and No. 298126. We acknowledge the computational resources provided by Aalto Science-IT project. The MEGA simulation used resources of the National Energy Research Scientific Computing Center (NERSC), a U.S. Department of Energy Office of Science User Facility located at Lawrence Berkeley National Laboratory, operated under Contract No. DE-AC02-05CH11231. Publisher Copyright: © 2021 American Physical Society. Fast ion phase-space flow, driven by Alfvén eigenmodes (AEs), is measured by an imaging neutral particle analyzer in the DIII-D tokamak. The flow firstly appears near the minimum safety factor at the injection energy of neutral beams, and then moves radially inward and outward by gaining and losing energy, respectively. The flow trajectories in phase space align well with the intersection lines of the constant magnetic moment surfaces and constant E-(ω/n)Pζ surfaces, where E, Pζ are the energy and canonical toroidal momentum of ions; ω and n are angular frequencies and toroidal mode numbers of AEs. It is found that the flow is so destructive that the thermalization of fast ions is no longer observed in regions of strong interaction. The measured phase-space flow is consistent with nonlinear hybrid kinetic-magnetohydrodynamics simulation. Calculations of the relatively narrow phase-space islands reveal that fast ions must transition between different flow trajectories to experience large-scale phase-space transport.

The potential formation of multi-mega-ampere beams of relativistic "runaway" electrons (REs) during sudden terminations of tokamak plasmas poses a significant challenge to the tokamak's development as a fusion energy source. Here, we use state-of-the-art modeling of disruption magnetohydrodynamics coupled with a self-consistent evolution of RE generation and transport to show that a non-axisymmetric in-vessel coil will passively prevent RE beam formation during disruptions in the SPARC tokamak, a compact, high-field, high-current device capable of achieving a fusion gain Q > 2 in deuterium-tritium plasmas.

Funding Information: The author (X. D. Du) would like to thank F. Zonca and L. Chen for fruitful discussions. This work was supported by the US DOE under DE-AC05-00OR22725, DE-FC02-04ER54698, DE-AC02-09CH11466, DE-SC0015878, and DE-SC0018287. Publisher Copyright: © 2021 American Physical Society. A thermal ion driven bursting instability with rapid frequency chirping, considered as an Alfvénic ion temperature gradient mode, has been observed in plasmas having reactor-relevant temperature in the DIII-D tokamak. The modes are excited over a wide spatial range from macroscopic device size to microturbulence size and the perturbation energy propagates across multiple spatial scales. The radial mode structure is able to expand from local to global in ∼0.1 ms and it causes magnetic topology changes in the plasma edge, which can lead to a minor disruption event. Since the mode is typically observed in the high ion temperature ≳10 keV and high-β plasma regime, the manifestation of the mode in future reactors should be studied with development of mitigation strategies, if needed. This is the first observation of destabilization of the Alfvén continuum caused by the compressibility of ions with reactor-relevant ion temperature.

JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become a widely used versatile code for studying large-scale plasma instabilities and their control developed in an international community. This article gives a comprehensive overview of the physics models implemented, numerical methods applied for solving the equations and physics studies performed with the code. A dedicated section highlights some of the verification work done for the code. A hierarchy of different physics models is available including a free boundary and resistive wall extension and hybrid kinetic-fluid models. The code allows for flux-surface aligned iso-parametric finite element grids in single and double X-point plasmas which can be extended to the true physical walls and uses a robust fully implicit time stepping. Particular focus is laid on plasma edge and scrape-off layer (SOL) physics as well as disruption related phenomena. Among the key results obtained with JOREK regarding plasma edge and SOL, are deep insights into the dynamics of edge localized modes (ELMs), ELM cycles, and ELM control by resonant magnetic perturbations, pellet injection, as well as by vertical magnetic kicks. Also ELM free regimes, detachment physics, the generation and transport of impurities during an ELM, and electrostatic turbulence in the pedestal region are investigated. Regarding disruptions, the focus is on the dynamics of the thermal quench and current quench triggered by massive gas injection (MGI) and shattered pellet injection (SPI), runaway electron (RE) dynamics as well as the RE interaction with MHD modes, and vertical displacement events (VDEs). Also the seeding and suppression of tearing modes (TMs), the dynamics of naturally occurring thermal quenches triggered by locked modes, and radiative collapses are being studied., Comment: Comprehensive review published as special topic article in Nuclear Fusion

Potential loss of energetic ions including alphas and radio-frequency tail ions due to classical orbit effects and magnetohydrodynamic instabilities (MHD) are central physics issues in the design and experimental physics programme of the SPARC tokamak. The expected loss of fusion alpha power due to ripple-induced transport is computed for the SPARC tokamak design by the ASCOT and SPIRAL orbit-simulation codes, to assess the expected surface heating of plasma-facing components. We find good agreement between the ASCOT and SPIRAL simulation results not only in integrated quantities (fraction of alpha power loss) but also in the spatial, temporal and pitch-angle dependence of the losses. If the toroidal field (TF) coils are well-aligned, the SPARC edge ripple is small (0.15–0.30 %), the computed ripple-induced alpha power loss is small ( ${\sim } 0.25\,\%$ ) and the corresponding peak surface power density is acceptable ( $244\ \textrm{kW}\ \textrm {m}^{-2}$ ). However, the ripple and ripple-induced losses increase strongly if the TF coils are assumed to suffer increasing magnitudes of misalignment. Surface heat loads may become problematic if the TF coil misalignment approaches the centimetre level. Ripple-induced losses of the energetic ion tail driven by ion cyclotron range of frequency (ICRF) heating are not expected to generate significant wall or limiter heating in the nominal SPARC plasma scenario. Because the expected classical fast-ion losses are small, SPARC will be able to observe and study fast-ion redistribution due to MHD including sawteeth and Alfvén eigenmodes (AEs). SPARC's parameter space for AE physics even at moderate $Q$ is shown to reasonably overlap that of the demonstration power plant ARC (Sorbom et al., Fusion Engng Des., vol. 100, 2015, p. 378), and thus measurements of AE mode amplitude, spectrum and associated fast-ion transport in SPARC would provide relevant guidance about AE behaviour expected in ARC.

The electron runaway phenomenon in plasmas depends sensitively on the momentum-space dynamics. However, efficient simulation of the global evolution of systems involving runaway electrons typically requires a reduced fluid description. This is needed for example in the design of essential runaway mitigation methods for tokamaks. In this paper, we present a method to include the effect of momentum-dependent spatial transport in the runaway avalanche growth rate. We quantify the reduction of the growth rate in the presence of electron diffusion in stochastic magnetic fields and show that the spatial transport can raise the effective critical electric field. Using a perturbative approach we derive a set of equations that allows treatment of the effect of spatial transport on runaway dynamics in the presence of radial variation in plasma parameters. This is then used to demonstrate the effect of spatial transport in current quench simulations for ITER-like plasmas with massive material injection. We find that in scenarios with sufficiently slow current quench, due to moderate impurity and deuterium injection, the presence of magnetic perturbations reduces the final runaway current considerably. Perturbations localized at the edge are not effective in suppressing the runaways, unless the runaway generation is off-axis, in which case they may lead to formation of strong current sheets at the interface of the confined and perturbed regions., Comment: 26 pages, 9 figures

We present various techniques that make orbit-following Monte Carlo simulations faster and more reliable when assessing collisionless fast particle losses due to magnetic field perturbations. These techniques are based on identifying various loss channels in constants of motion space using the so-called loss maps. We demonstrate that this allows one to attribute losses quantitatively to different transport mechanisms, increase signal-to-noise ratio when estimating FILD signal and peak power loads, and connect magnetic field structure directly to fast particle losses. Furthermore, we show that collisionless fast particle transport can be treated as an advection-diffusion process where the transport coefficients can be evaluated with the orbit-following method. Applying these techniques has the potential to make orbit-following simulations faster to perform, or to avoid them completely, while making the results more reliable as they become more clearly connected to underlying physics. We demonstrate these techniques for ITER by showing how alpha particle losses are affected by various magnetic field perturbations, estimating ICRH losses in reduced field scenarios, and performing a scan on alpha particle losses as a function of ELM control coil current phases., Draft used for reference. Subject to minor edits before submitting to a journal

Experimental observations, as well as theoretical predictions, indicate that the transport of energetic electrons decreases with energy. This reduction in transport is attributed to finite orbit width (FOW) effects. Using orbit-following simulations in perturbed tokamak magnetic fields that have an ideal homogeneous stochastic layer at the edge, we quantify the energy dependence of energetic electrons transport and confirm previous theoretical estimates. However, using magnetic configurations characteristic of JET disruptions, we find no reduction in runaway electron transport at higher energies, which we attribute to the mode widths being comparable to the minor radius, making the FOW effects negligible. Instead, the presence of islands and non-uniform magnetic perturbations are found to be more important. The diffusive-advective transport coefficients calculated in this work, based on simulations for electron energies 10 keV–100 MeV, can be used in integrated disruption modelling to account for the transport due to the magnetic field perturbations.

openaire: EC/H2020/633053/EU//EUROfusion The limits for the heat loads on the DEMO first wall are significantly stricter compared to those of ITER due to cooling and breeding blanket requirements. Fast particles in the form of NBI ions can escape the confinement due to magnetic perturbations and produce a significant power load on the first wall. In this contribution, we use the fast ion orbit-following code ASCOT to study NBI losses under the effects of 3D magnetic perturbations, including toroidal field ripple and ferritic inserts. The losses were found to not endanger the integrity of the wall, with loads remaining below 40 kW/m 2 even with unmitigated ripple, and losses did not increase above 2.5 % even with 16 toroidal field coils. Ionization in the scrape-off layer was not found to increase the losses significantly for realistic density profiles, and the design of the wall allows for some flexibility in the distance between the plasma and the first wall tiles.

Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle the role of plasma fueling and plasma shape for the onset of small ELM regimes. On both devices, small ELM regimes with high confinement are achieved if and only if two conditions are fulfilled at the same time. Firstly, the plasma density at the separatrix must be large enough (), leading to a pressure profile flattening at the separatrix, which stabilizes type-I ELMs. Secondly, the magnetic configuration has to be close to a double null (DN), leading to a reduction of the magnetic shear in the extreme vicinity of the separatrix. As a consequence, its stabilizing effect on ballooning modes is weakened. Peer Reviewed Article escrit per 365 autors/autores: Labit, B.; Eich, T.; Harrer, G. F.; Wolfrum, E.; Bernert, M.; Dunne, M. G.; Frassinetti, L.; Hennequin, P.; Maurizio, R.; Merle, A.; Meyer, H.; Saarelma, S.; Sheikh, U.; Adamek, J.; Agostini, M.; Aguiam, D.; Akers, R.; Albanese, R.; Albert, C.; Alessi, E.; Ambrosino, R.; Andr be, Y.; Angioni, C.; Apruzzese, G.; Aradi, M.; Arnichand, H.; Auriemma, F.; Avdeeva, G.; Ayllon-Guerola, J. M.; Bagnato, F.; Bandaru, V. K.; Barnes, M.; Barrera-Orte, L.; Bettini, P.; Bilato, R.; Biletskyi, O.; Bilkova, P.; Bin, W.; Blanchard, P.; Blanken, T.; Bobkov, V.; Bock, A.; Boeyaert, D.; Bogar, K.; Bogar, O.; Bohm, P.; Bolzonella, T.; Bombarda, F.; Boncagni, L.; Bouquey, F.; Bowman, C.; Brezinsek, S.; Brida, D.; Brunetti, D.; Bucalossi, J.; Buchanan, J.; Buermans, J.; Bufferand, H.; Buller, S.; Buratti, P.; Burckhart, A.; Calabr, G.; Calacci, L.; Camenen, Y.; Cannas, B.; Cano Megías, P.; Carnevale, D.; Carpanese, F.; Carr, M.; Carralero, D.; Carraro, L.; Casolari, A.; Cathey, A.; Causa, F.; Cavedon, M.; Cecconello, M.; Ceccuzzi, S.; Cerovsky, J.; Chapman, S.; Chmielewski, P.; Choi, D.; Cianfarani, C.; Ciraolo, G.; Coda, S.; Coelho, R.; Colas, L.; Colette, D.; Cordaro, L.; Cordella, F.; Costea, S.; Coster, D.; Cruz Zabala, D. J.; Cseh, G.; Czarnecka, A.; Cziegler, I.; D’Arcangelo, O.; Dal Molin, A.; David, P.; De Carolis, G.; De Oliveira, H.; Decker, J.; Dejarnac, R.; Delogu, R.; Den Harder, N.; Dimitrova, M.; Dolizy, F.; Domínguez-Palacios Durán, J. J.; Douai, D.; Drenik, A.; Dreval, M.; Dudson, B.; Dunai, D.; Duval, B. P.; Dux, R.; Elmore, S.; Embréus, O.; Erds, B.; Fable, E.; Faitsch, M.; Fanni, A.; Farnik, M.; Faust, I.; Faustin, J.; Fedorczak, N.; Felici, F.; Feng, S.; Feng, X.; Ferreira, J.; Ferr, G.; Février, O.; Ficker, O.; Figini, L.; Figueiredo, A.; Fil, A.; Fontana, M.; Francesco, M.; Fuchs, C.; Futatani, S.; Gabellieri, L.; Gadariya, D.; Gahle, D.; Galassi, D.; Gałązka, K.; Galdon-Quiroga, J.; Galeani, S.; Gallart, D.; Gallo, A.; Galperti, C.; Garavaglia, S.; Garcia, J.; Garcia-Lopez, J.; Garcia-Mu oz, M.; Garzotti, L.; Gath, J.; Geiger, B.; Giacomelli, L.; Giannone, L.; Gibson, S.; Gil, L.; Giovannozzi, E.; Giruzzi, G.; Gobbin, M.; Gonzalez-Martin, J.; Goodman, T. P.; Gorini, G.; Gospodarczyk, M.; Granucci, G.; Grekov, D. 1; Grenfell, G.; Griener, M.; Groth, M.; Grover, O.; Gruca, M.; Gude, A.; Guimarais, L.; Gyergyek, T.; Hacek, P.; Hakola, A.; Ham, C.; Happel, T.; Harrison, J.; Havranek, A.; Hawke, J.; Henderson, S.; Hesslow, L.; Hitzler, F.; Hnat, B.; Hobirk, J.; Hoelzl, M.; Hogeweij, D.; Hopf, C.; Hoppe, M.; Horacek, J.; Hron, M.; Huang, Z.; Iantchenko, A.; Iglesias, D.; Igochine, V.; Innocente, P.; Ionita-Schrittwieser, C.; Isliker, H.; Ivanova-Stanik, I.; Jacobsen, A.; Jakubowski, M.; Janky, F.; Jardin, A.; Jaulmes, F.; Jensen, T.; Jonsson, T.; Kallenbach, A.; Kappatou, A.; Karpushov, A.; Kasilov, S.; Kazakov, Y.; Kazantzidis, P. V.; Keeling, D.; Kelemen, M.; Kendl, A.; Kernbichler, W.; Kirk, A.; Kocsis, G.; Komm, M.; Kong, M.; Korovin, V.; Koubiti, M.; Kovacic, J.; Krawczyk, N.; Krieger, K.; Kripner, L.; Křivská, A.; Kudlacek, O.; Kulyk, Y.; Kurki-Suonio, T.; Kwiatkowski, R.; Laggner, F.; Laguardia, L.; Lahtinen, A.; Lang, P.; Likonen, J.; Lipschultz, B.; Liu, F.; Lombroni, R.; Lorenzini, R.; Loschiavo, V. P.; Lunt, T.; MacUsova, E.; Madsen, J.; Maggiora, R.; Maljaars, B.; Manas, P.; Mantica, P.; Mantsinen, M. J.; Manz, P.; Maraschek, M.; Marchenko, V.; Marchetto, C.; Mariani, A.; Marini, C.; Markovic, T.; Marrelli, L.; Martin, P.; Martín Solís, J. R.; Martitsch, A.; Mastrostefano, S.; Matos, F.; Matthews, G.; Mayoral, M.-L.; Mazon, D.; Mazzotta, C.; Mc Carthy, P.; McClements, K.; McDermott, R.; McMillan, B.; Meineri, C.; Menkovski, V.; Meshcheriakov, D.; Messmer, M.; Micheletti, D.; Milanesio, D.; Militello, F.; Miron, I. G.; Mlynar, J.; Moiseenko, V.; Molina Cabrera, P. A.; Morales, J.; Moret, J.-M.; Moro, A.; Moulton, D.; Nabais, F.; Naulin, V.; Naydenkova, D.; Nem, R. D.; Nespoli, F.; Newton, S.; Nielsen, A. H.; Nielsen, S. K.; Nikolaeva, V.; Nocente, M.; Nowak, S.; Oberkofler, M.; Ochoukov, R.; Ollus, P.; Olsen, J.; Omotani, J.; Ongena, J.; Orain, F.; Orsitto, F. P.; Paccagnella, R.; Palha, A.; Panaccione, L.; Panek, R.; Panjan, M.; Papp, G.; Paradela Perez, I.; Parra, F.; Passeri, M.; Pau, A.; Pautasso, G.; Pavlichenko, R.; Perek, A.; Pericoli Radolfini, V.; Pesamosca, F.; Peterka, M.; Petrzilka, V.; Piergotti, V.; Pigatto, L.; Piovesan, P.; Piron, C.; Piron, L.; Plyusnin, V.; Pokol, G.; Poli, E.; Pölöskei, P.; Popov, T.; Popovic, Z.; Pór, G.; Porte, L.; Pucella, G.; Puiatti, M. E.; Pütterich, T.; Rabinski, M.; Juul Rasmussen, J.; Rasmussen, J.; Rattá, G. A.; Ratynskaia, S.; Ravensbergen, T.; Réfy, D.; Reich, M.; Reimerdes, H.; Reimold, F.; Reiser, D.; Reux, C.; Reznik, S.; Ricci, D.; Rispoli, N.; Rivero-Rodriguez, J. F.; Rocchi, G.; Rodriguez-Ramos, M.; Romano, A.; Rosato, J.; Rubinacci, G.; Rubino, G.; Ryan, D. A.; Salewski, M.; Salmi, A.; Samaddar, D.; Sanchis-Sanchez, L.; Santos, J.; Särkimäki, K.; Sassano, M.; Sauter, O.; Scannell, R.; Scheffer, M.; Schneider, B. S.; Schneider, P.; Schrittwieser, R.; Schubert, M.; Seidl, J.; Seliunin, E.; Sharapov, S.; Sheeba, R. R.; Sias, G.; Sieglin, B.; Silva, C.; Sipilä, S.; Smith, S.; Snicker, A.; Solano, E. R.; Hansen, S. K.; Soria-Hoyo, C.; Sorokovoy, E.; Sozzi, C.; Sperduti, A.; Spizzo, G.; Spolaore, M.; Stejner, M.; Stipani, L.; Stober, J.; Strand, P.; Sun, H.; Suttrop, W.; Sytnykov, D.; Szepesi, T.; Tál, B.; Tala, T.; Tardini, G.; Tardocchi, M.; Teplukhina, A.; Terranova, D.; Testa, D.; Theiler, C.; Thorén, E.; Thornton, A.; Tilia, B.; Tolias, P.; Tomes, M.; Toscano-Jimenez, M.; Tsironis, C.; Tsui, C.; Tudisco, O.; Urban, J.; Valisa, M.; Vallar, M.; Vallejos Olivares, P.; Valovic, M.; Van Vugt, D.; Vanovac, B.; Varje, J.; Varju, J.; Varoutis, S. 1; Vartanian, S.; Vasilovici, O.; Vega, J.; Verdoolaege, G.; Verhaegh, K.; Vermare, L.; Vianello, N.; Vicente, J.; Viezzer, E.; Villone, F.; Voitsekhovitch, I.; Voltolina, D.; Vondracek, P.; Vu, N. M. T.; Walkden, N.; Wauters, T.; Weiland, M.; Weinzettl, V.; Wensing, M.; Wiesen, S.; Wiesenberger, M.; Wilkie, G.; Willensdorfer, M.; Wischmeier, M.; Wu, K.; Xiang, L.; Zagorski, R.; Zaloga, D.; Zanca, P.; Zaplotnik, R.; Zebrowski, J.; Zhang, W.; Zisis, A.; Zoletnik, S.; Zuin, M.

We report an accessible and robust tool for evaluating the effects of Coulomb collisions on a test particle in a plasma that obeys Maxwell–Juttner statistics. The implementation is based on the Beliaev–Budker collision integral which allows both the test particle and the background plasma to be relativistic. The integration method supports adaptive time stepping, which is shown to greatly improve the computational efficiency. The Monte Carlo method is implemented for both the three-dimensional particle momentum space and the five-dimensional guiding center phase space. Detailed description is provided for both the physics and implementation of the operator. The focus is in adaptive integration of stochastic differential equations, which is an overlooked aspect among existing Monte Carlo implementations of Coulomb collision operators. We verify that our operator converges to known analytical results and demonstrate that careless implementation of the adaptive time step can lead to severely erroneous results. The operator is provided as a self-contained Fortran 95 module and can be included into existing orbit-following tools that trace either the full Larmor motion or the guiding center dynamics. The adaptive time-stepping algorithm is expected to be useful in situations where the collision frequencies vary greatly over the course of a simulation. Examples include the slowing-down of fusion products or other fast ions, and the Dreicer generation of runaway electrons as well as the generation of fast ions or electrons with ion or electron cyclotron resonance heating. Program summary Program Title: AMCC –(A)daptive (M)onte-(C)arlo (C)oulomb collisions Program Files doi: http://dx.doi.org/10.17632/wd3t3t6dy7.1 Licensing provisions: MIT licence Programming language: Fortran 95 Nature of problem: Test-particle tracing is a common feat within existing fusion applications. While efficient adaptive methods exist for integrating the incompressible Hamiltonian flow, the effects of Coulomb collisions are commonly implemented with far less sophisticated algorithms. Solution method: The relativistic Fokker–Planck equation for test-particles in Maxwell–Juttner background plasmas is converted into a stochastic differential equation. The stochastic differential equation is solved using adaptive Monte Carlo techniques. Methods to evaluate the effect of Coulomb collisions for both the three-dimensional particle momentum space and the five-dimensional reduced guiding center phase space are included. Additional comments including restrictions and unusual features: The package includes optionality to evaluate the relativistic Fokker–Planck coefficients, a feature useful for constructing accurate orbit averaged collision operators. The package also provides explicit one-step symplectic integrator for the relativistic Lorentz force that can be used for tracing test-particles in given electromagnetic backgrounds.

In the four-stage approach of the new ITER Research Plan, the first pre-fusion power operation (PFPO) phase will only have limited power available from external heating and current drive (H&CD) systems: 20-30 MW provided by the electron cyclotron resonance heating (ECRH) system. Accessing the H-mode confinement regime at such low auxiliary power requires operating at low magnetic field, plasma current and density, i.e. 1.8 T and 5 MA for a density between 40% and 50% of the Greenwald density. II-mode plasmas at 5 MA/1.8 T will also be investigated in the second PFPO phase when ITER will have its full complement of H&CD capabilities installed, i.e. 20-30 MW of ECRH, 20 MW of ion cyclotron resonance heating and 33 MW of neutral beam injection. This paper describes the operational constraints and the II&CD capabilities for such scenarios in hydrogen and helium plasmas, to assess their viability and the issues it will be possible to address with them. The modelling results show that 5 MA/1.8 T scenarios are viable and will allow the exploration of the H-mode physics and control issues foreseen in the ITER Research Programme in the PFPO phases.

Mitigating edge localized modes (ELMs) with resonant magnetic perturbations (RMPs) can increase energetic particle losses and resulting wall loads, which have previously been studied in the vacuum approximation. This paper presents recent results of fusion alpha and NBI ion losses in the ITER baseline scenario modelled with the Monte Carlo orbit following code ASCOT in a realistic magnetic field including the effect of the plasma response. The response was found to reduce alpha particle losses but increase NBI losses, with up to 4.2% of the injected power being lost. Additionally, some of the load in the divertor was found to be shifted away from the target plates toward the divertor dome.

We assess the effect of the European design of the pebble-bed helium-cooled test blanket modules (TBM) on fast ion power loads on ITER material surfaces. For this purpose, the effect of not only the TBMs but also the ferritic inserts (FI), used for mitigating the toroidal field ripple, were included in unprecedented detail in the reconstruction of the 3-dimensional magnetic field. This is important because, due to their low collisionality, fast ions follow the magnetic geometry much more faithfully than the thermal plasma. The Monte Carlo orbit-following code ASCOT was used to simulate all the foreseen operating scenarios of ITER: the baseline 15 MA standard H-mode operation, the 12.5 MA hybrid scenario, the 9 MA advanced scenario, and the half-field scenario with helium plasma that will be ITER’s initial operating scenario. The effect of TBMs was assessed by carrying out the simulations in pairs: one including only the effect of ferritic inserts, and the other including also the perturbation due to TBMs. Both thermonuclear fusion alphas and NBI ions from ITER heating beams were addressed. The TBMs are found to increase the power loads, but the absolute values remain small. Neither do they produce any additional hot spots.

The magnetic perturbation due to the ferromagnetic test blanket modules (TBMs) may deteriorate fast ion confinement in ITER. This effect must be quantified by numerical studies in 3D. We have implemented a combined finite element method (FEM) -- Biot-Savart law integrator method (BSLIM) to calculate the ITER 3D magnetic field and vector potential in detail. Unavoidable geometry simplifications changed the mass of the TBMs and ferritic inserts (FIs) up to 26%. This has been compensated for by modifying the nonlinear ferromagnetic material properties accordingly. Despite the simplifications, the computation geometry and the calculated fields are highly detailed. The combination of careful FEM mesh design and using BSLIM enables the use of the fields unsmoothed for particle orbit-following simulations. The magnetic field was found to agree with earlier calculations and revealed finer details. The vector potential is intended to serve as input for plasma shielding calculations., In proceedings of the 28th Symposium on Fusion Technology

This paper addresses the confinement of thermonuclear alpha particles and neutral beam injected deuterons in the 15 MA Q = 10 inductive scenario in the presence of the magnetic perturbation caused by the helium cooled pebble bed test blanket module using the vacuum approximation. Both the flat top phase and plasma ramp-up are studied. The transport of fast ions is calculated using the Monte Carlo guiding center orbit-following code ASCOT. A detailed three-dimensional wall, derived from the ITER blanket module CAD data, is used for evaluating the fast ion wall loads. The effect of the test blanket module is studied for both overall confinement and possible hot spots. The study indicates that the test blanket modules do not significantly deteriorate the fast ion confinement.

The fusion alpha and beam ion with steady-state power loads in all four main operating scenarios of ITER have been evaluated by the ASCOT code. For this purpose, high-fidelity magnetic backgrounds were reconstructed, taking into account even the internal structure of the ferritic inserts and tritium breeding modules (TBM). The beam ions were found to be almost perfectly confined in all scenarios, and only the so-called hybrid scenario featured alpha loads reaching 0.5 MW due to its more triangular plasma. The TBMs were not found to jeopardize the alpha confinement, nor cause any hot spots. Including plasma response did not bring dramatic changes to the load. The ELM control coils (ECC) were simulated in the baseline scenario and found to seriously deteriorate even the beam confinement. However, the edge perturbation in this case is so large that the sources have to be re-evaluated with plasma profiles that take into account the ECC perturbation.

Computations in toroidal geometry are systematically performed for the plasma response to 3D magnetic perturbations produced by ferritic inserts (FIs) and test blanket modules (TBMs) for four ITER plasma scenarios: the 15 MA baseline, the 12.5 MA hybrid, the 9 MA steady state, and the 7.5 MA half-field helium plasma. Due to the broad toroidal spectrum of the FI and TBM fields, the plasma response for all the n = 1–6 field components are computed and compared. The plasma response is found to be weak for the high-n (n > 4) components. The response is not globally sensitive to the toroidal plasma flow speed, as long as the latter is not reduced by an order of magnitude. This is essentially due to the strong screening effect occurring at a finite flow, as predicted for ITER plasmas. The ITER error field correction coils (EFCC) are used to compensate the n = 1 field errors produced by FIs and TBMs for the baseline scenario for the purpose of avoiding mode locking. It is found that the middle row of the EFCC, with a suitable toroidal phase for the coil current, can provide the best correction of these field errors, according to various optimisation criteria. On the other hand, even without correction, it is predicted that these n = 1 field errors will not cause substantial flow damping for the 15 MA baseline scenario.

Disruption-generated runaway electrons (RE) present an outstanding issue for ITER. The predictive computational studies of RE generation rely on orbit-averaged computations and, as such, they lack the effects from the magnetic field stochasticity. Since stochasiticity is naturally present in post-disruption plasma, and externally induced stochastization offers a prominent mechanism to mitigate RE avalanche, we present an advection-diffusion model that can be used to couple an orbit-following code to an orbit-averaged tool in order to capture the cross-field transport and to overcome the latter's limitation. The transport coefficients are evaluated via a Monte Carlo method. We show that the diffusion coefficient differs significantly from the well-known Rechester-Rosenbluth result. We also demonstrate the importance of including the advection: it has a two-fold role both in modelling transport barriers created by magnetic islands and in amplifying losses in regions where the islands are not present.

The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and tested the technical and procedural preparation for safe operation with tritium. Research along three complementary axes yielded a wealth of new results. Firstly, the JET plasma programme delivered scenarios suitable for high fusion power and alpha particle (a) physics in the coming D–T campaign (DTE2), with record sustained neutron rates, as well as plasmas for clarifying the impact of isotope mass on plasma core, edge and plasma-wall interactions, and for ITER pre-fusion power operation. The efficacy of the newly installed shattered pellet injector for mitigating disruption forces and runaway electrons was demonstrated. Secondly, research on the consequences of long-term exposure to JET-ILW plasma was completed, with emphasis on wall damage and fuel retention, and with analyses of wall materials and dust particles that will help validate assumptions and codes for design and operation of ITER and DEMO. Thirdly, the nuclear technology programme aiming to deliver maximum technological return from operations in D, T and D–T benefited from the highest D–D neutron yield in years, securing results for validating radiation transport and activation codes, and nuclear data for ITER. 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 and 2019–2020 under Grant Agreement No. 633053. Peer Reviewed Article signat per 1223 autors/autores: J. Mailloux1, N. Abid1, K. Abraham1, P. Abreu2, O. Adabonyan1, P. Adrich3, V. Afanasev4, M. Afzal1, T. Ahlgren5, L. Aho-Mantila6, N. Aiba7, M. Airila6, M. Akhtar1, R. Albanese8, M. Alderson-Martin1, D. Alegre9, S. Aleiferis10, A. Aleksa1, A.G. Alekseev11, E. Alessi12, P. Aleynikov13, J. Algualcil14, M. Ali1, M. Allinson1, B. Alper1, E. Alves2, G. Ambrosino8, R. Ambrosino8, V. Amosov15, E.Andersson Sunden16, P. Andrew13, B.M. Angelini17, C. Angioni18, I. Antoniou1, L.C. Appel1, C. Appelbee1, S. Aria1, M. Ariola8, G. Artaserse17, W. Arter1, V. Artigues18, N. Asakura7, A. Ash1, N. Ashikawa19, V. Aslanyan20, M. Astrain21, O. Asztalos22, D. Auld1, F. Auriemma23, Y. Austin1, L. Avotina24, E. Aymerich25, A. Baciero9, F. Bairaktaris26, J. Balbin27, L. Balbinot23, I. Balboa1, M. Balden18, C. Balshaw1, N. Balshaw1, V.K. Bandaru18, J. Banks1, Yu.F. Baranov1, C. Barcellona28, A. Barnard1, M. Barnard1, R. Barnsley13, A. Barth1, M. Baruzzo17, S. Barwell1, M. Bassan13, A. Batista2, P. Batistoni17, L. Baumane24, B. Bauvir13, L. Baylor29, P.S. Beaumont1, D. Beckett1, A. Begolli1, M. Beidler29, N. Bekris30,31, M. Beldishevski1, E. Belli32, F. Belli17, É. Belonohy1, M. Ben Yaala33, J. Benayas1, J. Bentley1, H. Bergsåker34, J. Bernardo2, M. Bernert18, M. Berry1, L. Bertalot13, H. Betar35, M. Beurskens36, S. Bickerton1, B. Bieg37, J. Bielecki38, A. Bierwage7, T. Biewer29, R. Bilato18, P. Bílková39, G. Birkenmeier18, H. Bishop1, J.P.S. Bizarro2, J. Blackburn1, P. Blanchard40, P. Blatchford1, V. Bobkov18, A. Boboc1, P. Bohm39, T. Bohm41, I. Bolshakova42, T. Bolzonella23, N. Bonanomi18, D. Bonfiglio23, X. Bonnin13, P. Bonofiglo43, S. Boocock1, A. Booth1, J. Booth1, D. Borba2,30, D. Borodin44, I. Borodkina39,44, C. Boulbe45, C. Bourdelle27, M. Bowden1, K. Boyd1, I.Bozicevic Mihalic46, S.C. Bradnam1, V. Braic47, L. Brandt48, R. Bravanec49, B. Breizman50, A. Brett1, S. Brezinsek44, M. Brix1, K. Bromley1, B. Brown1, D. Brunetti1,12, R. Buckingham1, M. Buckley1, R. Budny, J. Buermans51, H. Bufferand27, P. Buratti17, A. Burgess1, A. Buscarino28, A. Busse1, D. Butcher1, E.de la Cal9, G. Calabrò52, L. Calacci53, R. Calado2, Y. Camenen54, G. Canal55, B. Cannas25, M. Cappelli17, S. Carcangiu25, P. Card1, A. Cardinali17, P. Carman1, D. Carnevale53, M. Carr1, D. Carralero9, L. Carraro23, I.S. Carvalho2, P. Carvalho2, I. Casiraghi56, F.J. Casson1, C. Castaldo17, J.P. Catalan14, N. Catarino2, F. Causa12, M. Cavedon18, M. Cecconello16, C.D. Challis1, B. Chamberlain1, C.S. Chang43, A. Chankin18, B. Chapman1,57, M. Chernyshova58, A. Chiariello8, P. Chmielewski58, A. Chomiczewska58, L. Chone59, G. Ciraolo27, D. Ciric1, J. Citrin60, Ł. Ciupinski61, M. Clark1, R. Clarkson1, C. Clements1, M. Cleverly1, J.P. Coad1, P. Coates1, A. Cobalt1, V. Coccorese8, R. Coelho2, J.W. Coenen44, I.H. Coffey62, A. Colangeli17, L. Colas27, C. Collins29, J. Collins1, S. Collins1, D. Conka24, S. Conroy16, B. Conway1, N.J. Conway1, D. Coombs1, P. Cooper1, S. Cooper1, C. Corradino28, G. Corrigan1, D. Coster18, P. Cox1, T. Craciunescu63, S. Cramp1, C. Crapper1, D. Craven1, R. Craven1, M.Crialesi Esposito48, G. Croci56, D. Croft1, A. Croitoru63, K. Crombe51,64, T. Cronin1, N. Cruz2, C. Crystal32, G. Cseh22, A. Cufar65, A. Cullen1, M. Curuia66, T. Czarski58, H. Dabirikhah1, A.Dal Molin56, E. Dale1, P. Dalgliesh1, S. Dalley1, J. Dankowski38, P. David18, A. Davies1, S. Davies1, G. Davis1, K. Dawson1, S. Dawson1, I.E. Day1, M. De Bock13, G. De Temmerman13, G. De Tommasi8, K. Deakin1, J. Deane1, R. Dejarnac39, D. Del Sarto35, E. Delabie29, D. Del-Castillo-Negrete29, A. Dempsey67, R.O. Dendy1,57, P. Devynck27, A. Di Siena18, C. Di Troia17, T. Dickson1, P. Dinca63, T. Dittmar44, J. Dobrashian1, R.P. Doerner68, A.J.H. Donne´69, S. Dorling1, S. Dormido-Canto70, D. Douai27, S. Dowson1, R. Doyle67, M. Dreval71, P. Drewelow36, P. Drews44, G. Drummond1, Ph. Duckworth13, H. Dudding1,72, R. Dumont27, P. Dumortier51, D. Dunai22, T. Dunatov46, M. Dunne18, I. Duran39, F. Durodie51, R. Dux18, A. Dvornova27, R. Eastham1, J. Edwards1, Th. Eich18, A. Eichorn1, N. Eidietis32, A. Eksaeva44, H. El Haroun1, G. Ellwood13, C. Elsmore1, O. Embreus73, S. Emery1, G. Ericsson16, B. Eriksson16, F. Eriksson74, J. Eriksson16, L.G. Eriksson75, S. Ertmer44, S. Esquembri21, A.L. Esquisabel76, T. Estrada9, G. Evans1, S. Evans1, E. Fable18, D. Fagan1, M. Faitsch18, M. Falessi17, A. Fanni25, A. Farahani1, I. Farquhar1, A. Fasoli40, B. Faugeras45, S. Fazinic46, F. Felici40, R. Felton1, A. Fernandes2, H. Fernandes2, J. Ferrand1, D.R. Ferreira2, J. Ferreira2, G. Ferrò53, J. Fessey1, O. Ficker39, A.R. Field1, A. Figueiredo2, J. Figueiredo2,30, A. Fil1, N. Fil1,20, P. Finburg1, D. Fiorucci23, U. Fischer31, G. Fishpool1, L. Fittill1, M. Fitzgerald1, D. Flammini17, J. Flanagan1, K. Flinders1, S. Foley1, N. Fonnesu17, M. Fontana40, J.M. Fontdecaba9, S. Forbes1, A. Formisano8, T. Fornal58, L. Fortuna28, E. Fortuna-Zalesna61, M. Fortune1, C. Fowler1, E. Fransson74, L. Frassinetti34, M. Freisinger44, R. Fresa8, R. Fridström34, D. Frigione53, T. Fülöp73, M. Furseman1, V. Fusco24, S. Futatani17, D. Gadariya77, K. Gál69, D. Galassi40, K. Gałazka58, S. Galeani53, D. Gallart78, R. Galvao55, Y. Gao44, J. Garcia27, M. García-Muñoz79, M. Gardener1, L. Garzotti1, J. Gaspar80, R. Gatto81, P. Gaudio53, D. Gear1, T. Gebhart29, S. Gee1, M. Gelfusa53, R. George1, S.N. Gerasimov1, G. Gervasini12, M. Gethins1, Z. Ghani1, M. Gherendi63, F. Ghezzi12, J.C. Giacalone27, L. Giacomelli12, G. Giacometti54, C. Gibson1, K.J. Gibson72, L. Gil2, A. Gillgren74, D. Gin4, E. Giovannozzi17, C. Giroud1, R. Glen1, S. Glöggler18, J. Goff1, P. Gohil32, V. Goloborodko82, R. Gomes2, B. Gonçalves2, M. Goniche27, A. Goodyear1, S. Gore1, G. Gorini56, T. Görler18, N. Gotts1, R. Goulding43, E. Gow1, B. Graham1, J.P. Graves40, H. Greuner18, B. Grierson43, J. Griffiths1, S. Griph1, D. Grist1, W. Gromelski58, M. Groth59, R. Grove29, M. Gruca58, D. Guard1, N. Gupta1, C. Gurl1, A. Gusarov83, L. Hackett1, S. Hacquin27,30, R. Hager43, L. Hägg16, A. Hakola6, M. Halitovs24, S. Hall1, S.A. Hall1, S. Hallworth-Cook1, C.J. Ham1, D. Hamaguchi7, M. Hamed27, C. Hamlyn-Harris1, K. Hammond1, E. Harford1, J.R. Harrison1, D. Harting1, Y. Hatano84, D.R. Hatch50, T. Haupt1, J. Hawes1, N.C. Hawkes1, J. Hawkins1, T. Hayashi7, S. Hazael1, S. Hazel1, P. Heesterman1, B. Heidbrink85, W. Helou13, O. Hemming1, S.S. Henderson1, R.B. Henriques2, D. Hepple1, J. Herfindal29, G. Hermon1, J. Hill1, J.C. Hillesheim1, K. Hizanidis26, A. Hjalmarsson16, A. Ho60, J. Hobirk18, O. Hoenen13, C. Hogben1, A. Hollingsworth1, S. Hollis1, E. Hollmann68, M. Hölzl18, B. Homan45, M. Hook1, D. Hopley1, J. Horácek39, D. Horsley1, N. Horsten59, A. Horton1, L.D. Horton30,40, L. Horvath1,72, S. Hotchin1, R. Howell1, Z. Hu56, A. Huber44, V. Huber44, T. Huddleston1, G.T.A. Huijsmans13, P. Huynh27, A. Hynes1, M. Iliasova4, D. Imrie1, M. Imrísek39, J. Ingleby1, P. Innocente23, K. Insulander Björk73, N. Isernia8, I. Ivanova-Stanik58, E. Ivings1, S. Jablonski58, S. Jachmich13,30,51, T. Jackson1, P. Jacquet1, H. Järleblad86, F. Jaulmes39, J.Jenaro Rodriguez1, I. Jepu63, E. Joffrin27, R. Johnson1, T. Johnson34, J. Johnston1, C. Jones1, G. Jones1, L. Jones1, N. Jones1, T. Jones1, A. Joyce1, R. Juarez14, M. Juvonen1, P. Kalnin¸ a24, T. Kaltiaisenaho6, J. Kaniewski1, A. Kantor1, A. Kappatou18, J. Karhunen5, D. Karkinsky1, Yu Kashchuk87, M. Kaufman29, G. Kaveney1, Ye.O. Kazakov51, V. Kazantzidis26, D.L. Keeling1, R. Kelly1, M. Kempenaars13, C. Kennedy1, D. Kennedy1, J. Kent1, K. Khan1, E. Khilkevich4, C. Kiefer18, J. Kilpeläinen59, C. Kim32, Hyun-Tae Kim1,30, S.H. Kim13, D.B. King1, R. King1, D. Kinna1, V.G. Kiptily1, A. Kirjasuo6, K.K. Kirov1, A. Kirschner44, T. kiviniemi59, G. Kizane24, M. Klas88, C. Klepper29, A. Klix31, G. Kneale1, M. Knight1, P. Knight1, R. Knights1, S. Knipe1, M. Knolker32, S. Knott89, M. Kocan13, F. Köchl1, I. Kodeli65, Y. Kolesnichenko82, Y. Kominis26, M. Kong1, V. Korovin71, B. Kos65, D. Kos1, H.R. Koslowski44, M. Kotschenreuther50, M. Koubiti54, E. Kowalska-Strzeciwilk ˛ 58, K. Koziol3, A. Krasilnikov87, V. Krasilnikov13,15, M. Kresina1,27, K. Krieger18, N. Krishnan1, A. Krivska51, U. Kruezi13, I. Ksia˛zek ˙ 90, A.B. Kukushkin11, H. Kumpulainen59, T. Kurki-Suonio59, H. Kurotaki7, S. Kwak36, O.J. Kwon91, L. Laguardia12, E. Lagzdina24, A. Lahtinen5, A. Laing1, N. Lam1, H.T. Lambertz44, B. Lane1, C. Lane1, E.Lascas Neto40, E. Łaszynska58, K.D. Lawson1, A. Lazaros26, E. Lazzaro12, G. Learoyd1, Chanyoung Lee92, S.E. Lee84, S. Leerink59, T. Leeson1, X. Lefebvre1, H.J. Leggate67, J. Lehmann1, M. Lehnen13, D. Leichtle31,93, F. Leipold13, I. Lengar65, M. Lennholm1,75, E. Leon Gutierrez9, B. Lepiavko82, J. Leppänen6, E. Lerche51, A. Lescinskis24, J. Lewis1, W. Leysen83, L. Li44, Y. Li44, J. Likonen6, Ch. Linsmeier44, B. Lipschultz72, X. Litaudon27,30, E. Litherland-Smith1, F. Liu27,30, T. Loarer27, A. Loarte13, R. Lobel1, B. Lomanowski29, P.J. Lomas1, J.M. Lopez21, R. Lorenzini23, S. Loreti17, U. Losada9, V.P. Loschiavo8, M. Loughlin13, Z. Louka1, J. Lovell29, T. Lowe1, C. Lowry1,75, S. Lubbad1, T. Luce13, R. Lucock1, A. Lukin94, C. Luna95, E.de la Luna9, M. Lungaroni53, C.P. Lungu63, T. Lunt18, V. Lutsenko82, B. Lyons32, A. Lyssoivan51, M. Machielsen40, E. Macusova39, R. Mäenpää59, C.F. Maggi1, R. Maggiora96, M. Magness1, S. Mahesan1, H. Maier18, R. Maingi43, K. Malinowski58, P. Manas18,54, P. Mantica12, M.J. Mantsinen97, J. Manyer78, A. Manzanares98, Ph. Maquet13, G. Marceca40, N. Marcenko87, C. Marchetto99, O. Marchuk44, A. Mariani12, G. Mariano17, M. Marin60, M. Marinelli53, T. Markovicˇ39, D. Marocco17, L. Marot33, S. Marsden1, J. Marsh1, R. Marshall1, L. Martellucci53, A. Martin1, A.J. Martin1, R. Martone8, S. Maruyama13, M. Maslov1, S. Masuzaki19, S. Matejcik88, M. Mattei8, G.F. Matthews1, D. Matveev44, E. Matveeva39, A. Mauriya2, F. Maviglia8, M. Mayer18, M.-L. Mayoral1,69, S. Mazzi54, C. Mazzotta17, R. McAdams1, P.J. McCarthy89 K.G. McClements1, J. McClenaghan32, P. McCullen1, D.C. McDonald1, D. McGuckin1, D. McHugh1, G. McIntyre1, R. McKean1, J. McKehon1, B. McMillan57, L. McNamee1, A. McShee1, A. Meakins1, S. Medley1, C.J. Meekes60,100, K. Meghani1, A.G. Meigs1, G. Meisl18, S. Meitner29, S. Menmuir1, K. Mergia10, S. Merriman1, Ph. Mertens44, S. Meshchaninov15, A. Messiaen51, R. Michling57, P. Middleton1, D. Middleton-Gear1, J. Mietelski38, D. Milanesio96, E. Milani53, F. Militello1, A.Militello Asp1, J. Milnes1, A. Milocco56, G. Miloshevsky101, C. Minghao1, S. Minucci52, I. Miron63, M. Miyamoto102, J. Mlynár39,103, V. Moiseenko71, P. Monaghan1, I. Monakhov1, T. Moody1, S. Moon34, R. Mooney1, S. Moradi51, J. Morales27, R.B. Morales1, S. Mordijck104, L. Moreira1, L. Morgan1, F. Moro17, J. Morris1, K.-M. Morrison1, L. Msero13,33, D. Moulton1, T. Mrowetz1, T. Mundy1, M. Muraglia54, A. Murari23,30, A. Muraro12, N. Muthusonai1, B. N’Konga45, Yong-Su Na92, F. Nabais2, M. Naden1, J. Naish1, R. Naish1, F. Napoli17, E. Nardon27, V. Naulin86, M.F.F. Nave2, I. Nedzelskiy3, G. Nemtsev15, V. Nesenevich4, I. Nestoras1, R. Neu18, V.S. Neverov11, S. Ng1, M. Nicassio1, A.H. Nielsen86, D. Nina2, D. Nishijima105, C. Noble1, C.R. Nobs1, M. Nocente56, D. Nodwell1, K. Nordlund5, H. Nordman13, R. Normanton1, J.M. Noterdaeme18, S. Nowak12, E. Nunn1, H. Nyström34, M. Oberparleiter74, B. Obryk38, J. O’Callaghan1, T. Odupitan1, H.J.C. Oliver1,50, R. Olney1, M. O’Mullane106, J. Ongena51, E. Organ1, F. Orsitto8, J. Orszagh88, T. Osborne32, R. Otin1, T. Otsuka107, A. Owen1, Y. Oya108, M. Oyaizu7, R. Paccagnella23, N. Pace1, L.W. Packer1, S. Paige1, E. Pajuste24, D. Palade63, S.J.P. Pamela1, N. Panadero9, E. Panontin56, A. Papadopoulos26, G. Papp18, P. Papp88, V.V. Parail1, C. Pardanaud54, J. Parisi1,109, F.Parra Diaz109, A. Parsloe1, M. Parsons29, N. Parsons1, M. Passeri53, A. Patel1, A. Pau40, G. Pautasso18, R. Pavlichenko71, A. Pavone36, E. Pawelec90, C.Paz Soldan110, A. Peacock1,75, M. Pearce1, E. Peluso53, C. Penot13, K. Pepperell1, R. Pereira2, T. Pereira2, E.Perelli Cippo12, P. Pereslavtsev107, C. Perez von Thun58, V. Pericoli58, D. Perry1, M. Peterka39, P. Petersson34, G. Petravich22, N. Petrella1, M. Peyman1, M. Pillon17, S. Pinches13, G. Pintsuk44, W. Pires de Sá55, A. Pires dos Reis55, C. Piron17, L. Pionr23,111, A. Pironti8, R. Pitts13, K.L. van de Plassche60, N. Platt1, V. Plyusnin2, M. Podesta43, G. Pokol22, F.M. Poli43, O.G. Pompilian63, S. Popovichev1, M. Poradzinski58, M.T. Porfiri17, M. Porkolab20, C. Porosnicu63, M. Porton1, G. Poulipoulis112, I. Predebon23, G. Prestopino53, C. Price1, D. Price1, M. Price1, D. Primetzhofer16, P. Prior1, G. Provatas46, G. Pucella17, P. Puglia40, K. Purahoo1, I. Pusztai73, O. Putignano56, T. Pütterich18, A. Quercia8, E. Rachlew73, G. Radulescu29, V. Radulovic65, M. Rainford1, P. Raj31, G. Ralph1, G. Ramogida17, D. Rasmussen29, J.J. Rasmussen86, G. Rattá9, S. Ratynskaia113, M. Rebai12, D. Refy22, R. Reichle13, M. Reinke29, D. Reiser44, C. Reux27, S. Reynolds1, M.L. Richiusa1, S. Richyal1, D. Rigamonti12, F.G. Rimini1, J. Risner29, M. Riva17, J. Rivero-Rodriguez79, C.M. Roach1, R. Robins1, S. Robinson1, D. 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Sipilä59, A.C.C. Sips75, P. Siren5, A. Sirinelli13, H. Sjöstrand16, N. Skinner1, J. Slater1, N. Smith1, P. Smith1, J. Snell1, G. Snoep60, L. Snoj65, P. Snyder32, S. Soare63, E.R. Solano9, V. Solokha59, A. Somers67, C. Sommariva40, K. Soni33, E. Sorokovoy71, M. Sos39, J. Sousa2, C. Sozzi12, S. Spagnolo23, T. Spelzini1, F. Spineanu63, D. Spong29, D. Sprada1, S. Sridhar27, C. Srinivasan1, G. Stables1, G. Staebler32, I. Stamatelatos10, Z. Stancar65, P. Staniec1, G. Stankunas116, M. Stead1, E. Stefanikova34, A. Stephen1, J. Stephens1, P. Stevenson1, M. Stojanov1, P. Strand74, H.R. Strauss117, S. Strikwerda1, P. Ström34, C.I. Stuart1, W. Studholme1, M. Subramani1, E. Suchkov88, S. Sumida7, H.J. Sun1, T.E. Susts24, J. Svensson36, J. Svoboda39, R. Sweeney20, D. Sytnykov71, T. Szabolics22, G. Szepesi1, B. Tabia1, T. Tadic´46, B. Tál18, T. Tala6, A. Tallargio1, P. Tamain27, H. Tan1, K. Tanaka19, W. Tang43, M. Tardocchi12, D. Taylor1, A.S. Teimane24, G. Telesca58, N. Teplova4, A. Teplukhina43, D. Terentyev83, A. Terra44, D. Terranova23, N. Terranova17, D. Testa40, E. Tholerus1,34, J. Thomas1, E. Thoren113, A. Thorman1, W. Tierens18, R.A. Tinguely20, A. Tipton1, H. Todd1, M. Tokitani19, P. Tolias113, M. Tomes39, A. Tookey1, Y. Torikai118, U. von Toussaint18, P. Tsavalas10, D. Tskhakaya39,119, I. Turner1, M. Turner1, M.M. Turner67, M. Turnyanskiy1,69, G. Tvalashvili1, S. Tyrrell1, M. Tyshchenko82, A. Uccello12, V. Udintsev13, G. Urbanczyk27, A. Vadgama1, D. Valcarcel1, M. Valisa23, P.Vallejos Olivares34, O. Vallhagen73, M. Valovicˇ1, D. Van Eester51, J. Varje59, S. Vartanian27, T. Vasilopoulou10, G. Vayakis13, M. Vecsei22, J. Vega9, S. Ventre8, G. Verdoolaege64, C. Verona53, G.Verona Rinati53, E. Veshchev13, N. Vianello23, E. Viezzer79, L. Vignitchouk113, R. Vila9, R. Villari17, F. Villone8, P. Vincenzi23, I. Vinyar94, B. Viola17, A.J. Virtanen59, A. Vitins24, Z. Vizvary1, G. Vlad17, M. Vlad63, P. Vondrácek39, P.de Vries13, B. Wakeling1, N.R. Walkden1, M. 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Zychor3 // 1 United Kingdom Atomic Energy Authority, Culham Science Centre, Abingdon, Oxon, OX14 3DB, United Kingdom of Great Britain and Northern Ireland 2 Instituto de Plasmas e Fusao Nuclear, Instituto Superior Técnico, Universidade de Lisboa, 1049-001 Lisboa, Portugal 3 National Centre for Nuclear Research (NCBJ), 05-400 Otwock-Swierk, Poland 4 Ioffe Physico-Technical Institute, 26 Politekhnicheskaya, St Petersburg 194021, Russia 5 University of Helsinki, PO Box 43, FI-00014 University of Helsinki, Finland 6 VTT Technical Research Centre of Finland, PO Box 1000, FIN-02044 VTT, Finland 7 National Institutes for Quantum and Radiological Science and Technology, Naka, Ibaraki 311-0193, Japan 8 Consorzio CREATE, Via Claudio 21, 80125 Napoli, Italy 9 Laboratorio Nacional de Fusión, CIEMAT, Madrid, Spain 10 NCSR ‘Demokritos’ 153 10, Agia Paraskevi Attikis, Greece 11 NRC Kurchatov Institute, 1 Kurchatov Square, Moscow 123182, Russia 12 Institute for Plasma Science and Technology, CNR, via R. Cozzi 53, 20125 Milano, Italy 13 ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 Saint Paul Lez Durance Cedex, France 14 Universidad Nacional de Educacion a Distancia, Dept Ingn Energet, Calle Juan del Rosal 12, E-28040 Madrid, Spain 15 Troitsk Insitute of Innovating and Thermonuclear Research (TRINITI), Troitsk 142190, Moscow Region, Russia 16 Department of Physics and Astronomy, Uppsala University, SE-75120 Uppsala, Sweden 17 Dip.to Fusione e Tecnologie per la Sicurezza Nucleare, ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati (Roma), Italy 18 Max-Planck-Institut für Plasmaphysik, D-85748 Garching, Germany 19 National Institute for Fusion Science, Oroshi, Toki, Gifu 509-5292, Japan 20 MIT Plasma Science and Fusion Center, Cambridge, MA 02139, United States of America 21 Universidad Politécnica de Madrid, Grupo I2A2, Madrid, Spain 22 Centre for Energy Research, POB 49, H-1525 Budapest, Hungary 23 Consorzio RFX, Corso Stati Uniti 4, 35127 Padova, Italy 24 University of Latvia, 19 Raina Blvd., Riga, LV 1586, Latvia 25 Department of Electrical and Electronic Engineering, University of Cagliari, Piazza d’Armi 09123 Cagliari, Italy 26 National Technical University of Athens, Iroon Politechniou 9, 157 73 Zografou, Athens, Greece 27 CEA, IRFM, F-13108 Saint Paul Lez Durance, France 28 Dipartimento di Ingegneria Elettrica Elettronica e Informatica, Università degli Studi di Catania, 95125 Catania, Italy 29 Oak Ridge National Laboratory, Oak Ridge, TN 37831, TN, United States of America 30 EUROfusion Programme Management Unit, Culham Science Centre, Culham, OX14 3DB, United Kingdom of Great Britain and Northern Ireland 31 Karlsruhe Institute of Technology, PO Box 3640, D-76021 Karlsruhe, Germany 32 General Atomics, PO Box 85608, San Diego, CA 92186-5608, United States of America 33 Department of Physics, University of Basel, Switzerland 34 Fusion Plasma Physics, EECS, KTH Royal Institute of Technology, SE-10044 Stockholm, Sweden 35 Institut Jean Lamour, UMR 7198, CNRS-Université de Lorraine, 54500 Vandoeuvre-lès-Nancy, France 36 Max-Planck-Institut für Plasmaphysik, Teilinsitut Greifswald, D-17491 Greifswald, Germany 37 Maritime University of Szczecin Faculty of Marine Engineering, Waly Chrobrego 1-2, 70-500 Szczecin, Poland 38 Institute of Nuclear Physics, Radzikowskiego 152, 31-342 Kraków, Poland 39 Institute of Plasma Physics of the CAS, Za Slovankou 1782/3, 182 00 Praha 8, Czech Republic 40 Ecole Polytechnique Fédérale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland 41 University of Wisconsin-Madison, Madison, WI 53706, United States of America 42 Magnetic Sensor Laboratory, Lviv Polytechnic National University, Lviv, Ukraine 43 Princeton Plasma Physics Laboratory, James Forrestal Campus, Princeton, NJ 08543, NJ, United States of America 44 Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung, Plasmaphysik, 52425 Jülich, Germany 45 Université Cote d’Azur, CNRS, Inria, LJAD, Parc Valrose, 06108 Nice Cedex 02, France 46 Ruder Boskovic Institute, Bijenicka 54, 10000 Zagreb, Croatia 47 The National Institute for Optoelectronics, Magurele-Bucharest, Romania 48 Mechanics, SCI, KTH SE-100 44 Stockholm, Sweden 49 Fourth State Research, 503 Lockhart Dr, Austin, TX, United States of America 50 University of Texas at Austin, Institute for Fusion Studies, Austin, TX 78712, United States of America 51 Laboratory for Plasma Physics LPP-ERM/KMS, B-1000 Brussels, Belgium 52 University of Tuscia, DEIM, Via del Paradiso 47, 01100 Viterbo, Italy 53 Università di Roma Tor Vergata, Via del Politecnico 1, Roma, Italy 54 Aix-Marseille University, CNRS, PIIM, UMR 7345, 13013 Marseille, France 55 Instituto de Física, Universidade de Sao Paulo, Rua do Mat˜ao Travessa R Nr.187, CEP 05508-090 Cidade Universitária, Sao Paulo, Brasil 56 University of Milano-Bicocca, Piazza della Scienza 3, 20126 Milano, Italy 57 Centre for Fusion, Space and Astrophysics, University of Warwick, Coventry, CV4 7AL, United Kingdom of Great Britain and Northern Ireland 58 Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw, Poland 59 Aalto University, PO Box 14100, FIN-00076 Aalto, Finland 60 FOM Institute DIFFER, Eindhoven, The Netherlands 61 Warsaw University of Technology, 02-507 Warsaw, Poland 62 Astrophysics Research Centre, School of Mathematics and Physics, Queen’s University, Belfast, BT7 1NN, United Kingdom of Great Britain and Northern Ireland 63 The National Institute for Laser, Plasma and Radiation Physics, Magurele-Bucharest, Romania 64 Department of Applied Physics, Ghent University, 9000 Ghent, Belgium 65 Slovenian Fusion Association (SFA), Jozef Stefan Institute, Jamova 39, SI-1000 Ljubljana, Slovenia 66 The National Institute for Cryogenics and Isotopic Technology, Ramnicu Valcea, Romania 67 Dublin City University (DCU), Dublin, Ireland 68 University of California at San Diego, La Jolla, CA 92093, United States of America 69 EUROfusion Programme Management Unit, Boltzmannstr. 2, 85748 Garching, Germany 70 UNED, Dpto. Informática y Automática, Madrid, Spain 71 National Science Center ‘Kharkov Institute of Physics and Technology’, Akademichna 1, Kharkiv 61108, Ukraine 72 York Plasma Institute, Department of Physics, University of York, York, YO10 5DD, United Kingdom of Great Britain and Northern Ireland 73 Department of Physics, Chalmers University of Technology, SE-41296 Gothenburg, Sweden 74 Department of Space, Earth and Environment, Chalmers University of Technology, SE-41296 Gothenburg, Sweden 75 European Commission, B-1049 Brussels, Belgium 76 University of Tennessee, Knoxville, TN 37996, TN, United States of America 77 Universitat Politècnica de Catalunya, Barcelona, Spain 78 Barcelona Supercomputing Center, Barcelona, Spain 79 Universidad de Sevilla, Sevilla, Spain 80 Aix-Marseille University, CNRS, IUSTI, UMR 7343, 13013 Marseille, France 81 Dipartimento di Ingegneria Astronautica, Elettrica ed Energetica, SAPIENZA Università di Roma, Via Eudossiana 18, 00184 Roma, Italy 82 Institute for Nuclear Research, Prospekt Nauky 47, Kyiv 03680, Ukraine 83 Studiecentrum voor Kernenergie—Centre d’Etude de l’Energie Nucléaire, Boeretang 200, 2400 Mol, Belgium 84 University of Toyama, Toyama, 930-8555, Japan 85 University of California, Irvine, Irvine, California 92697, United States of America 86 Department of Physics, Technical University of Denmark, Bldg 309, DK-2800 Kgs Lyngby, Denmark 87 Institution ‘Project Center ITER’, Moscow, 123182, Russia 88 Faculty of Mathematics, Department of Experimental Physics, Physics and Informatics Comenius University Mlynska dolina F2, 84248 Bratislava, Slovakia 89 University College Cork (UCC), Cork, Ireland 90 Institute of Physics, Opole University, Oleska 48, 45-052 Opole, Poland 91 Daegu University, Jillyang, Gyeongsan, Gyeongbuk 712-174, Republic of Korea 92 Department of Nuclear Engineering, Seoul National University, Seoul, Republic of Korea 93 Fusion for Energy Joint Undertaking, Josep Pl. 2, Torres Diagonal Litoral B3, 08019, Barcelona, Spain 94 PELIN LLC, 27a, Gzhatskaya Ulitsa, Saint Petersburg, 195220, Russia 95 Arizona State University, Tempe, AZ, United States of America 96 Politecnico di Torino, Corso Duca degli Abruzzi 24, I-10129 Torino, Italy 97 ICREA and Barcelona Supercomputing Center, Barcelona, Spain 98 Universidad Complutense de Madrid, Madrid, Spain 99 Istituto dei Sistemi Complessi—CNR and Dipartimento di Energia—Politecnico di Torino, C.so Duca degli Abruzzi 24, 10129 Torino, Italy 100 Eindhoven University of Technology, The Netherlands 101 Purdue University, 610 Purdue Mall, West Lafayette, IN 47907, United States of America 102 Department of Material Science, Shimane University, 1060 Nishikawatsu, Matsue, 690-8504, Japan 103 Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Brehová 78/7, 115 19 Praha 1, Czech Republic 104 College of William and Mary, Williamsburg, VA 23185, United States of America 105 University of California, 1111 Franklin St., Oakland, CA 94607, United States of America 106 University of Strathclyde, Glasgow, G4 0NG, United Kingdom of Great Britain and Northern Ireland 107 Kindai University, Higashi-Osaka, 577-8502, Japan 108 Shizuoka University, Shizuoka, 422-8529, Japan 109 Rudolf Peierls Centre for Theoretical Physics, University of Oxford, Oxford OX1 3PU, United Kingdom of Great Britain and Northern Ireland 110 Columbia University, New York, NY 10027, United States of America 111 Dipartimento di Fisica ‘G. Galilei’, Universita’ degli Studi di Padova, Padova, Italy 112 Space and Plasma Physics, EECS, KTH SE-100 44 Stockholm, Sweden 113 University of Ioannina, Panepistimioupoli Ioanninon, PO Box 1186, 45110 Ioannina, Greece 114 Universidade do Porto, Faculdade de Engenharia, 4200-465 Porto, Portugal 115 The University of Tokyo, Kashiwa, Chiba, 277-0882, Japan 116 Lithuanian Energy Institute, Breslaujos g. 3, LT-44403, Kaunas, Lithuania 117 HRS Fusion, West Orange, NJ, United States of America 118 Ibaraki University Graduate School of Science and Engineering, Mito, Ibaraki 310-8512, Japan 119 Technische Universität Wien, Fusion@ÖAW Österreichische Akademie der Wissenschaften (ÖAW), Austria