photo collage on cover page: hands‐on education at ... · was officially inaugurated on 3...
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Photo collage on cover page:
Hands‐on education at Austrian university laboratories.
Courtesy Technische Universität Wien, Institut für Angewandte Physik and Atominstitut, and
Universität Innsbruck, Institut für Ionenphysik und Angewandte Physik
Fusion Research in Austria
Activities in 2016 and 2017
Vienna April 2018
Fusion Research in Austria ‐ Activities in 2016 and 2017
Compiled by Monika Fischer This work has been partly 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
Supported by
Fusion@ÖAW Coordination Office
Apostelgasse 23
1030 Wien Austria
Tel. +43‐1‐51581‐2675
http://www.oeaw.ac.at/fusion
Copyright © 2018 by Austrian Academy of Sciences
Vienna Printed in Austria
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CONTENTS
INTRODUCTION .......................................................................................................................... 2
I. ON THE ROAD TO FUSION ENERGY ........................................................................................ 4
II. FUSION RESEARCH IN AUSTRIA ............................................................................................. 8
1. OVERVIEW …………………………………………………………………………………………………………………. 8
2. HIGHLIGHTS ……………………………………………………………………………………………………………… 10
3. FUSION EDUCATION …………………………………………………………………………………………………. 15
4. PUBLICATIONS…………………………………………………………………………………………………………. 20
MANAGEMENT STRUCTURE……………………………………………………………………………………………... 27
AUSTRIAN REPRESENTATIVES IN COMMITTEES RELEVANT FOR FUSION RESEARCH AND DEVELOPMENT (2016/2017) ………………………………………………………………………………………….... 28
ABBREVIATIONS AND ACRONYMS ………………………………………………………………………………….... 29
CONTACT INFORMATION ……………………………………………………………………………………………….....30
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INTRODUCTION
The construction of the ITER, the world’s largest fusion experiment
which will be the first device to produce net fusion energy, is
progressing well, with the first plasma scheduled for 2025. The
European Fusion Programme is strongly integrated and is presently preparing for the exploitation of
ITER and the design of DEMO along The Roadmap to the Realization of Fusion Energy, a document
which is constantly revised and adapted to current developments.
This brochure is intended to highlight the integration of Austrian fusion research into the European
Fusion Research Programme and make successes visible.
The largest part of Austrian fusion research is performed at university institutes, with approximately
21 PhD students and their supervisors participating per year. Education and training of young
researchers therefore continues to be an important objective of the Austrian Fusion Research
Programme, which is well recognized by the number of PhD theses supported within the EUROfusion
work package Education. Selected theses completed in the period 2016/2017 or near completion are
presented in chapter II.3.
As Austria does not have its own fusion facilities, opportunities to contribute to experiments and
modelling at JET, ASDEX Upgrade and Wendelstein 7‐X are vital for the successful participation of
Austrian scientists in the fusion programme. I would therefore like to commend the efforts by the
EUROfusion Programme Management Unit and task leaders to schedule and manage the
experimental campaigns under the work packages Small and Medium‐Sized Tokamaks (MST1 and
MST2) as well as the campaigns at JET.
The involvement of industry in the European Fusion Programme and the accessibility of business
opportunities triggered by the construction of ITER are of vital importance for the ITER project. In this
respect, valuable support is provided by the Industrial Liaison Officer (ILO) at the Austrian Federal
Economic Chamber who circulates information about calls and specialized meetings for industry to
qualified companies and organizes the participation of delegations from industry in specialized
meetings.
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Last, but not least I wish to thank all members of our Research Unit for their unbroken commitment
and enthusiasm and the institutions listed below for their cooperation and support:
the Austrian Ministry for Science, Research and Economy and its representatives
(as of January 2018, the Austrian Federal Ministry of Education, Science and Research)
the President, Presiding Committee and staff of ÖAW,
the Austrian Commission for the Coordination of Fusion Research at ÖAW, and
the responsible officers of the European Fusion Programme.
Vienna, February 2018 (Friedrich Aumayr
Head of Research Unit, Fusion@ÖAW)
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I. ON THE ROAD TO FUSION ENERGY
ITER The tokamak ITER —designed to demonstrate the scientific and technological feasibility of fusion power—will be the world's largest experimental fusion facility. ITER is built in international cooperation, with components delivered by the domestic agencies of all ITER partners (People’s Republic of China, European Union, India, Japan, Russian Federation, South Korea and United States of America). The ITER Organization and the seven Domestic Agencies are now working collectively to meet the milestones detailed in the new overall project schedule, which was approved by the ITER Council in November 2016.
During the period 2016/2017 there has been intensive construction work on the ITER site at Cadarache (in the south of France), and many heavy components have been delivered. Up‐to‐date photographs and videos can be viewed at https://www.iter.org/.
In August 2017, a temporary lid was installed between the basement and the upper levels of the ITER bioshield (concrete structure between the tokamak and the building hosting it) Copyright © ITER Organization http://www.iter.org
The European domestic agency ‐ Fusion for Energy (F4E)
F4E was established for a period of 35 years from 19 April 2007. On 4 December 2017 the organization celebrated its tenth anniversary together with about 500 participants representing F4E staff, cooperation partners and stakeholders. The event was honored by the presence of the European Commissioner for Climate Action and Energy, Miguel Arias Cañete. Fusion for Energy has its headquarters in Barcelona (Spain) and is responsible for providing the European Union’s contribution to ITER. Calls for tender, vacancies and up‐to‐date information on the progress of the ITER project are published on F4E’s website http://fusionforenergy.europa.eu/ .
Information for Austrian industry
Harnessing fusion energy is an industrial effort to be backed up by targeted research. It is the task of the network of Industrial Liaison Officers (ILOs) to raise awareness among qualified companies and advise them on ways to get involved in the ITER project. In cooperation with the ILOs, F4E organizes a series of information days and seminars to report on the roadmap of different procurement packages and facilitate partnerships between companies. In Austria the function of ILO is performed by the Austrian Federal Economic Chamber which acts as a contact forum for Austrian companies qualified for participating in high‐tech industrial projects.
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EUROfusion
In 2014, 29 research organizations from 27 countries (European Union and Switzerland) acceded to the EUROfusion Grant Agreement and signed the EUROfusion consortium agreement. At the beginning of 2017, the Ukrainian fusion research unit joined EUROfusion.
The first plasma in ITER is expected to be generated in 2025. To prepare for the experimental campaigns at ITER, EUROfusion manages campaigns at European tokamaks such as JET (Culham, UK), ASDEX Upgrade (IPP Garching, Germany), TCV (Lausanne, Switzerland) and MAST (Culham, UK) and coordinates the advancement of the fusion research base. With a view to future fusion power plants, Wendelstein 7‐X represents the largest device of the stellarator concept. Up‐to‐date information about recent results, news and vacancies within the European fusion research units can be found at https://www.euro‐fusion.org/ JET (CCFE, Culham, United Kingdom)
JET at the Culham Centre for Fusion Energy (CCFE) is presently the largest tokamak in the world and the only fusion experiment in operation which is capable of producing substantial amounts of fusion energy. EUROfusion provides the work platform for jointly exploiting JET in an efficient and focused way, managing experiments at JET within the annual work programmes of the ITER Physics Department.
An overview on first results from experiments with the ITER‐like wall (ILW) which was installed in JET in 2010/2011 is presented in X. Litaudon et al., “Overview of the JET results in support to ITER”, Nuclear Fusion 57 (2017), 102001 (41pp); co‐authors from Fusion@ÖAW: D. Tskhakaya (TU Wien) and V. Yavorskij (Universität Innsbruck). In this overview paper, the contribution of JET experiments in the period 2014‐2016 with the ITER first wall materials mix and the underlying physics understanding with improved diagnostics are reviewed in the context of optimizing the ITER Research Plan. Together with the ITER scenario development for deuterium–tritium (D–T) operation, a strong focus on JET utilization is pursued for addressing ITER needs and developing a sound physics basis for the extrapolation through first principle and integrated modelling.
Among the most important topics for investigation in JET are dust production (with the ILW two magnitudes lower than in the former carbon‐wall machine), erosion of tungsten components, and methods for ELM control to mitigate divertor erosion. At present, the JET programme focuses on the integrated preparation of the pure tritium and deuterium–tritium experiments scheduled for 2018 and 2019.
Virtual vessel of JET with plasma (blend of computerized imagery and photography). Source: https://www.euro‐fusion.org/
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Experiments at medium‐size tokamaks (MST) managed by EUROfusion
With the medium‐size tokamaks (MST) programme EUROfusion coordinates research on ASDEX Upgrade (AUG), MAST and TCV. This multi‐machine approach is instrumental to progress in the field, as ITER and DEMO core/pedestal and scrape‐off layer (SOL) parameters are not achievable simultaneously in present day devices. On the one hand, scenarios with tolerable transient heat and particle loads, including active edge localized mode (ELM) control are developed. On the other hand, divertor solutions including advanced magnetic configurations are studied. Considerable progress has been made on both approaches, in particular in the fields of ELM control with resonant magnetic perturbations (RMP), small ELM regimes, detachment onset and control as well as filamentary scrape‐off‐layer transport.
Results of the MST programme up to 2016 are presented in H. Meyer, “Overview of progress in European medium sized tokamaks towards an integrated plasma‐edge/wall solution”, Nuclear Fusion 57 (2017), 102014 (16 pp); co‐authors from Fusion@ÖAW: F. Laggner (TU Wien), S. Kasilov, W. Kernbichler, A. Martitsch (TU Graz), S. Costea, C. Ionita‐Schrittwieser, A. Kendl, R. Kube, B. Schneider, R. Schrittwieser and M. Wiesenberger ( Universität Innsbruck). ASDEX Upgrade (IPP Garching, Germany)
The ASDEX Upgrade tokamak at Max‐Planck Institut für Plasmaphysik in Garching near München (Germany) started operation in 1991. In 2002, ASDEX Upgrade was opened to use by fusion laboratories from all over Europe. In 2014, joint exploitation started in the framework of the Medium Sized Tokamak Programme (MST) of EUROfusion.
TCV (Swiss Plasma Center, Lausanne, Switzerland)
The Tokamak à Configuration Variable (TCV) started operation at École Polytechnique Fédérale de Lausanne (EFPL) in 1992. In 2015/2016 the machine was upgraded to enforce its capabilities such as strong shaping and electron heating with ion heating, additional electron heating compatible with high densities and variable divertor geometry. The TCV programme aims at ITER support, explorations towards DEMO and fundamental research.
Recent upgrades and experimental results are described in S. Coda et al., “Overview of the TCV tokamak program: scientific progress and facility upgrades”, Nuclear Fusion 57 (2017), 102011 (12pp); co‐authors from Fusion@ÖAW: S. Costea, C. Ionita‐Schrittwieser, B. Schneider and R. Schrittwieser (Universität Innsbruck).
ASDEX Upgrade vessel view during 2016 shut‐down. The new bellows protection plates and the modified support structure are installed. The labyrinth‐like protection plates are still missing as well as the protection plates for the lower ELM control coils and divertor targets
Source: http://www.ipp.mpg.de/ Image: IPP, A. Herrmann
d i 2016 h t
TCV tokamak at EPFL Image: Alain Herzog/EPFL
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MAST‐U (CCFE, Culham, United Kingdom)
The upgraded MAST facility at CCFE (UK) will be ready for experiments as of 2018. MAST‐U is a spherical tokamak which can explore a wide range of alternative divertor configurations. The plasma is heated using neutral beam injection and is equipped with ELM control coils and an extensive suite of diagnostics.
Wendelstein 7‐X
Wendelstein 7‐X, located in Greifswald (Germany), is the worldwide largest stellarator. After completion of the main assembly phase, the first plasma was achieved in December 2015. The facility was officially inaugurated on 3 February 2016 in the presence of the German chancellor Angela Merkel.
The main objective of the optimized stellarator Wendelstein 7‐X (W7‐X) is the demonstration of steady‐state plasma operation at fusion‐relevant plasma parameters, thereby verifying that the stellarator is a viable fusion power plant concept.
The first operational campaigns allowed for initial physics studies, including a first assessment of power balance and energy confinement, electron cyclotron resonant heating (ECRH) power deposition experiments, and current drive experiments using electron cyclotron current drive. As in many plasma discharges the electron temperature exceeds the ion temperature significantly, these plasmas are governed by core electron root confinement showing a strong positive electric field in the plasma center. Results of the first operational phase are summarized in R.C. Wolf et al., “Major results from the first plasma campaign of the Wendelstein 7‐X stellarator”, Nuclear Fusion 57 (2017), 102020 (13pp, co‐authors from Fusion@ÖAW: F. Köchl (TU Wien/CCFE) and R. Schrittwieser (Universität Innsbruck).
The inside of the stellarator Wendelstein 7‐X showing the reddish tiles made of copper‐chromium‐zirconium. Source: https://www.euro‐fusion.org/ Image: IPP http://www.ipp.mpg.de
Disruptions inside the plasma of MAST Source:https://www.euro-fusion.org/
Image: © protected by United Kingdom Atomic Energy Authority
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II. FUSION RESEARCH IN AUSTRIA
Activities in 2016 and 2017
1. OVERVIEW
The largest part of Austrian fusion research is performed at university institutes, with approximately 21 PhD students per year. Education and training of young researchers therefore continues to be the major focus of the Austrian Fusion Research Programme, building on strong cooperation with European fusion labs such as CCFE (Culham, United Kingdom), IPP Garching (Germany), EPFL (Lausanne, Switzerland), FZ Jülich and FZ Karlsruhe (Germany). Major activities/topics are measurements and experiments in medium‐size tokamaks, plasma‐wall interaction, modelling and simulation of plasma phenomena in tokamaks and stellarators, materials science, superconductors for fusion application and socio‐economic studies on future energy scenarios.
The major part of the Austrian fusion research programme is supported by EUROfusion. In addition, there have been small contracts with Fusion for Energy (carried out at Atominstitut/ TU Wien) and an advisory function within the ITER Fellowship of Fusion Science Programme (carried out at Institut für Angewandte Physik/ TU Wien).
Participation in EUROfusion
As programme manager of the Austrian participation the Austrian Academy of Sciences (ÖAW) acts as national entry point and beneficiary of the EUROfusion Grant Agreement. Fusion research is performed at the Erich Schmid Institute of Materials Science at ÖAW and at four linked parties: Research Studio iSPACE in Salzburg, Technische Universität Graz, Technische Universität Wien and Universität Innsbruck. The share of ÖAW and its linked third parties is shown below.
Austrian participation in EUROfusion: Share of ÖAW and Linked Third Parties (based on average expenditure 2016/2017;
source: Fusion@ÖAW)
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Participation in EUROfusion work packages Period: 2016/2017
PART OF THE PROGRAMME INSTITUTION SCIENTISTS INVOLVED
ITER PHYSICS
WP01 JET Campaigns (WPJET1) UIBK K. Schöpf
WP04 JET Enhancements (WPJET4) UIBK K. Schöpf
WP05 Medium‐Sized‐Tokamak Campaigns (WPMST1) TU Graz TU Wien UIBK
W. Kernbichler F. Aumayr A Kendl R. Schrittwieser
WP06 Preparation of the Exploitation of Medium‐Sized Tokamaks (WPMST2)
UIBK R. Schrittwieser C. Ionita
WP07 Preparation of efficient PFC operation for ITER and DEMO (WPPFC)
TU Wien TU Wien UIBK
F. Aumayr D. Tskhakaya M. Probst
WP11 Preparation and Exploitation of W7‐X Campaigns (WPS1)
TU Graz TU Wien UIBK
W. Kernbichler F. Köchl R. Schrittwieser
WP12 Stellarator optimization theory development, modelling and engineering (WPS2)
TU Graz W. Kernbichler
WP13 Code Development for integrated modelling (WPCD)
TU Wien UIBK
D. Tskhakaya M. Probst
POWER PLANT PHYSICS AND TECHNOLOGY
WP16 Magnet system (WPMAG) TU Wien M. Eisterer
WP25 Materials (WPMAT) ÖAW‐ESI TU Wien
R. Pippan H. Leeb
Socio‐Economic Research on Fusion (SERF)
WP28 Socio Economic studies (WPSES) Research Studios Austria FG
M. Biberacher
EDUCATION
WP30 Education (WPEDU) TU Graz ÖAW‐ESI TU Wien UIBK
20 PhD students 12 mentors
ENABLING RESEARCH (starting 2017)
WP32 Enabling Research (WPENR) TU Wien
M. Eisterer
Abbreviations: TU Graz = Graz University of Technology
TU Wien = Vienna University of Technology UIBK = University of Innsbruck ÖAW‐ESI = Erich Schmid Institute of Materials Science at ÖAW
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2. HIGHLIGHTS
WP05‐MST1: Medium‐Size Tokamaks
Experimental work – pedestal studies
The paper F M Laggner, E. Wolfrum, F Mink, E Viezzer, M G Dunne, P Manz, H Doerk, G Birkenmeier, R Fischer, S Fietz, M Maraschek, M Willensdorfer, F Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “High frequency magnetic fluctuations correlated with the inter‐ELM pedestal evolution in ASDEX Upgrade”, Plasma Physics and Controlled Fusion 58 (2016), https://doi.org/10.1088/0741‐3335/58/6/065005, was among the most popular articles downloaded in 2016 and was therefore selected as a Highlight of 2016 by IOP.
Research group: F. Aumayr et al., Institut für Angewandte Physik, TU Wien
Excerpt from Abstract: In order to understand the mechanisms that determine the structure of the high confinement mode (H‐mode) pedestal, the evolution of the plasma edge electron density and temperature profiles between edge localized modes (ELMs) was investigated. The magnetic fluctuation frequency detected at the onset of ELMS was analysed for a variety of plasma discharges with different electron pressure pedestals.
Figure 1. Pre‐ELM profiles of (a) the plasma edge electron density ne, (b) the electron temperature Te and (c) the ratio of electron to magnetic pressure βe. The shaded areas represent the propagated variation of the uncertainties in data evaluation and the standard deviation of the ELM‐synchronised average. Both discharges have similar βe profiles and vary in pedestal top electron collisionality ν∗e,ped.
Modelling and simulation
A.F. Martitsch, S.V. Kasilov, W. Kernbichler, G. Kapper, C.G. Albert, M.F. Heyn, H.M. Smith, E. Strum‐berger, S. Fietz, W. Suttrop, M. Landreman, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Effect of 3D magnetic perturbations on the plasma rotation in ASDEX Upgrade”, Plasma Physics and Controlled Fusion 58(7) 2016, https://doi.org/10.1088/0741‐3335/58/7/074007.
Research group: W. Kernbichler et al., Institut für Theoretische Physik – Computational Physics, TU Graz
Excerpt from Abstract: The toroidal torque due to the non‐resonant interaction with external magnetic perturbations (TF ripple and perturbations from ELM mitigation coils) in ASDEX Upgrade was modelled with the help of the NEO‐2 and SFINCS codes and compared to semi‐analytical models. It was shown that almost all non‐axisymmetric transport regimes contributing to neoclassical toroidal viscosity (NTV) were realized within a single discharge at different radial positions. The NTV torque was obtained to be roughly a quarter of the neutral beam injection (NBI) torque. This indicates the presence of other important momentum sources.
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Figure 2. Ion contribution to the NTV torque density produced by the ELM mitigation coils with a phase of 90 degrees as a function of the normalized poloidal radius. Neglecting the effect of magnetic drift (left), the NEO‐2 result (solid line) is compared to SFINCS (dashed line), to a semi‐analytical Hamiltonian model (dash–dotted line) and to the bounce‐averaged model by Shaing (dotted line). The NEO‐2 result including both, E × B drift and magnetic drift, is compared to the semi‐analytical Hamiltonian model taking into account drift‐orbit (do) and superbanana‐plateau (sbp) resonances.
WP06‐MST2: Preparation of the Exploitation of Medium‐Size Tokamaks
S. Costea, B. Fonda, J. Kovacic, T. Gyergyek, B. Schneider, R. Schrittwieser and and C. Ionita,” Bunker probe: a plasma potential probe almost insensitive to its orientation with the magnetic field”, Review of Scientific Instruments 87(5) 2016, http://dx.doi.org/10.1063/1.4951688 .
Research group: R. Schrittwieser, Institute für Ionenphysik und Angewandte Physik, UIBK
Excerpt from Abstract: Ion‐sensitive probes have the ability to suppress a large part of the electron current, thus measuring the plasma potential directly. For these probes to work, almost perfect alignment with the total magnetic field is necessary. As magnetic fields are curved, this condition cannot always be fulfilled. Under this perspective, a plasma potential probe (Bunker probe) based on the principle of the ion sensitive probe but almost insensitive to its orientation with the total magnetic field has been developed and tested by S. Costea, C. Ionita, R. Schrittwieser et al. The Bunker probe can be used to measure the plasma potential inside fusion devices, especially in regions with complex magnetic field topology.
Figure 3. Cross sections of the Bunker probe and trajectories of magnetically confined ions (blue, +) and electrons (red ‐ for different orientations of the probe with respect to the magnetic field (B, green arrow).
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WP07‐PFC: Preparation of Efficient PFC Operation for ITER and DEMO
B.M. Berger, R. Stadlmayr, D. Blöch, E. Gruber, K. Sugiyama, T. Schwarz‐Selinger and F. Aumayr, “Erosion of Fe‐W model systems under normal and oblige D Ion irradiation”, Nuclear Materials and Energy 12 (2017), https://doi.org/10.1016/j.nme.2017.03.030 .
Research group: F. Aumayr et al., Institut für Angewandte Physik, TU Wien
Excerpt from Abstract: The dynamic erosion behaviour of iron‐tungsten (Fe‐W) model films (with 1.5at% W) resulting from 250 eV deuterium (D) irradiation was investigated under well‐defined laboratory conditions. For three different impact angles (0°, 45° and 60°with respect to the surface normal) the erosion yield was monitored as a function of incident D fluence using a highly sensitive quartz crystal microbalance technique (QCM). In addition, the evolution of the Fe‐W film topography and roughness with increasing fluence was observed, using an atomic force microscope (AFM). The mass removal rate for Fe‐W is found to be comparable to the value of a pure Fe film at low incident fluences, but strongly decreases with increasing D fluence. This is consistent with earlier observations of a substantial W enrichment at the surface due to preferential Fe sputtering.
High resolution AFM images reveal that continued ion irradiation leads to significant surface roughening and formation of nano‐dots or nano‐ripples. This may indicate that the W enrichment at the surface due to preferential sputtering of Fe is not exclusively responsible for the observed reduction in erosion with increasing D fluence.
Figure 4. Evolution of the mass removal rate (mrr) of Fe‐W (1.5 at% W) and pure Fe films as a function of the applied D fluence (flc) for irradiation with 250 eV/D under normal impact ( α = 0° ). For low fluences the mass removal rate for Fe‐W is close to the value of pure Fe. With increasing fluence, a significant reduction of the Fe‐W mass removal rate is observed. The insets (a) and (b) show the mean slope of the mrr‐curve for 3 different impact angles (0° , 45° and 60° ) at fluences between 0 and 1∙ 1023 D/m2 (a) and at fluences between 2∙ 1023 D/m2 and 3∙ 1023 D/m2 (b). The shaded areas represent the estimated experimental errors.
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WP12‐S2: Stellarator Optimization
S.V. Kapper, V. Kasilov, W. Kernbichler, A. F. Martitsch, M. F. Heyn, N. B. Marushchenko and Y. Turkin, “Electron cyclotron current drive simulations for finite collisionality plasmas in Wendelstein 7‐X using the full linearized collision model”, Physics of Plasmas 23/11 (2016), https://doi.org/10.1063/1.4968234.
Research group: W. Kernbichler et al., Institut für Theoretische Physik – Computational Physics, TU Graz Excerpt from Abstract: While models of electron cyclotron current drive (ECCD) efficiency with
collisionless limits are sufficient for plasmas with low collisionality, they might underestimate the current drive in plasmas at low temperatures. In this paper, the impact of finite collisionality effects on the wave‐induced current drive is studied for a high mirror configuration of Wendelstein 7‐X using a combination of the drift kinetic equation solver NEO‐2 and the ray‐tracing code TRAVIS. The generalized Spitzer function is modeled with NEO‐2; results of the ray‐tracing code TRAVIS using the ECCD efficiency from NEO‐2 within the adjoint approach show a significant difference of the driven current as compared to commonly used collisionless models for the ordinary as well as the extraordinary second harmonic mode.
Figure 5. Scenario X2a ‐ Locally absorbed power dP/dl (left) and locally driven current dI/dl (right) for the finite collisionality and the collisionless case as functions of the distance along the central ray l. Contributions of passing and trapped particles are depicted as dashed and dotted lines, respectively. The cold resonance position is marked with a thick vertical line.
Figure 6. Scenario X2a ‐ Current density integral kernel as a function of the parallel and perpendicular normalized velocities for finite collisionality (left) and collisionless limit (right). The three numbered resonance lines correspond to respective positions indicated by numbered vertical lines in figure 5. The trapped passing boundary is shown by dashed lines. Colors are supersaturated in order to clarify the different signs of kernel F in different regions.
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WP13‐CD Code Development
Several codes for plasma modelling were developed at Austrian universities under the Contract of Association between EURATOM and the Austrian Academy of Sciences and the European Fusion Development Agreement (EFDA). Most of these codes became part of the Integrated Tokamak Modelling (ITM) Programme under EFDA and have been further upgraded and adapted under EUROfusion. Prominent examples are the codes BIT1 (D. Tskhakaya et al., Universität Innsbruck/ Technische Universität Wien), JINTRAC (F. Köchl et al., Technische Universität Wien in cooperation with CEA) and NEO‐2 (W. Kernbichler et al., Technische Universität Graz in cooperation with IPP Garching).
In a joint effort of all contributors to the work package Code Development, workflows involving at least two edge codes have progressed beyond the 2015 prototype, which coupled the plasma‐wall interaction and impurity transport code ERO to SOLPS. In 2016, the main scheme for workflows coupling SOLPS to ERO and BIT1 was devised. As from 2017, ITER and EUROfusion cooperate to develop the Integrated Modelling and Analysis Suite (IMAS).
Scenario modelling with JINTRAC
S. Wiesen, F. Koechl, P. Belo, V. Kotov, A. Loarte, V. Parail, G. Corrigan, L. Garzotti and D. Harting, “Control of particle and power exhaust in pellet fuelled ITER DT scenarios employing integrated models”, Nuclear Fusion 57 (2017), https://doi.org/10.1088/1741‐4326/aa6ecc
Research group: M. Eisterer, Atominstitut, TU Wien
Excerpt from Abstract: The integrated model JINTRAC is employed to assess the dynamic density evolution of the ITER baseline scenario when fuelled by discrete pellets. The consequences on the core confinement properties, α‐particle heating due to fusion and the effect on the ITER divertor operation, taking into account the material limitations on the target heat loads, are discussed within the integrated model.
It is concluded that integrated models like JINTRAC, if validated and supported by realistic physics constraints, may help to establish suitable control schemes of particle and power exhaust in burning ITER DT‐plasma scenarios.
Figure 7. Time transients of critical divertor detachment characteristics for the modelled ITER high‐density
baseline scenarios case with 60 MW radiative fraction in the SOL and top pedestal 1.05 ∙ 1020 m−3. The time‐axis starts at the beginning of the JINTRAC simulation (t = 0 s) which began from a non‐detached plasma‐state. As simulation time advances, the divertor plasma is driven into a detached state (as seen from the particle flux Γtarg roll‐over and drop in qtarg). In the saturated phase after 0.5 s, regular pellet injections are triggered when the main plasma falls below the minimum density d = 1.05 ∙ 1020 m−3. These cause a transient reduction of the degree of detachment shortly after pellet ablation times.
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3. FUSION EDUCATION
Given that in Austria the main contribution to the EUROfusion work programme is made by universities, Fusion@ÖAW considers “education of the generation ITER” as its most important mission. The institutions participating in the Austrian Fusion Research Programme offer mentoring to a yearly average of 20 PhD students working on fusion‐relevant PhD‐theses.
Selected PhD theses completed /near completion in 2016/2017
ITER physics
Medium‐size tokamaks ‐ pedestal physics and ELMs
Inter ELM pedestal structure development in ASDEX Upgrade (completed: May 2017)
F. Laggner, Institut für Angewandte Physik, TU Wien; Supervisor: F. Aumayr
At the edge of magnetically confined fusion plasmas, a steep pressure gradient occurs that forms the so‐called pedestal and is limited by edge localized modes (ELMs). The objective of this thesis was to understand how the pedestal temporally evolves between ELMs and when the stability limit is reached. Moreover the structure of the pedestal (height and width of the pressure gradient) in plasma with different main ion species was investigated.
The detailed investigation of the pedestal recovery phases after an ELM crash showed for the first time that the sequence of recovery phases evolves independently of main ion species, plasma collisionality and plasma shape until the stability limit is reached. It was also shown that the fast increase of the electron‐density pedestal is not dominated by the neutral dynamics in the divertor or main chamber because it occurs on faster timescales. The magnetic fluctuations, occurring in the pre‐ELM phase with constant pressure gradient, were characterized in detail for the first time. It has been shown that the underlying instability is located close to the minimum of the radial electric field, shows a toroidal mode number of 11 and is also detectable on the high‐field side.
Publications in scientific journals in 2016/2017 (first author):
F.M. Laggner, E. Wolfrum, M. Cavedon, F. Mink, E. Viezzer, M.G. Dunne, P. Manz, H. Doerk, G. Birkenmeier, R. Fischer, S. Fietz, M. Maraschek, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “High frequency magnetic fluctuations correlated with the inter‐ELM pedestal evolution in ASDEX Upgrade”, Plasma Phys. Control. Fusion 58 (2016), https://doi.org/10.1088/0741‐3335/58/6/065005, selected by IOP as Highlight of 2016.
F.M. Laggner, E. Wolfrum, M. Cavedon, F. Mink, M. Bernert, M.G. Dunne, P.A. Schneider, A. Kappatou, G. Birkenmeier, R. Fischer, M. Willensdorfer, F. Aumayr, EUROfusion MST1 Team and ASDEX Upgrade Team, “Pedestal structure and inter‐ELM evolution for different main ion species in ASDEX Upgrade“, Physics of Plasmas 24 (2017), http://dx.doi.org/10.1063/1.4977461.
F.M. Laggner, S. Keerl, J. Gnilsen, E. Wolfrum, M. Bernert, D. Carralero, L. Guimarais, V. Nikolaeva, S. Potzel, M. Cavedon, F. Mink, M.G. Dunne, G. Birkenmeier, R. Fischer, E. Viezzer, M. Willensdorfer, M. Wischmeier, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Divertor, scrape‐off layer and pedestal particle dynamics in the ELM cycle on ASDEX Upgrade”, Plasma Physics and Controlled fusion 60/2 (2017), https://doi.org/10.1088/1361‐6587/aa90bf.
F.M. Laggner, E. Wolfrum, M. Cavedon, M.G. Dunne, G. Birkenmeier, R. Fischer, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Plasma shaping and its impact on the pedestal of ASDEX Upgrade: Edge stability and inter‐ELM dynamics at varied triangularity”, submitted to Nuclear Fusion.
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Plasma‐facing components
Laboratory work on plasma‐wall‐interaction processes relevant for fusion experiments (completed May 2017)
B. Berger, Institut für Angewandte Physik, TU Wien; Supervisor: F. Aumayr
To pave the way towards a future fusion power plant it is crucial to develop a first wall that can withstand the high heat fluxes and energetic particle bombardment long enough to ensure economical operation of the power plant. To gain deeper insight on erosion processes, fusion‐relevant plasma‐wall‐interactions were studied under controlled laboratory conditions, using a highly sensitive quartz crystal microbalance (QCM) technique.
One of projectile‐target combinations investigated within this thesis is the erosion of tungsten‐nitride (WN) by deuterium (D) ions. In a future fusion device, impurity seeding into the plasma is required to reduce the power flux to the divertor. Nitrogen seeding is an effective coolant at the plasma edge. In combination with a tungsten (W) divertor, the formation of WN surface layers is observed. In this work the erosion of
WN and W films was studied under D ion bombardment at 500 and 1000eV/D. For W a constant erosion rate was measured with increasing D fluence, whereas for WN an initially enhanced erosion rate was observed, until steady state conditions were reached. Simulations of this process indicate that the initially higher erosion rate of WN is caused by enhanced N erosion.
In addition, fluence dependent sputter experiments were carried out for thin iron‐tungsten (FeW) films under 250 and 1000 eV/D ion bombardment (1.5 at% W). FeW is a model system for heavy‐element containing steels (e.g. EUROFER), which are considered as possible materials for recessed areas in a future fusion reactor. In particular, The incident angle of the ion beam was varied for 250 eV and the sample’s topography and roughness was investigated before and after the exposure to a total fluence of 3 ∙ 1023 D/m2. The initially more pronounced reduction of the erosion yield for oblique ion impact, vanishes with increasing fluence and reaches the value of normal incidence. This effect is related to a significant surface roughening and the formation of nano‐dots or nano‐ripples. Publications in scientific journals in 2016/2017 (first author):
B.M. Berger, R. Stadlmayr, G. Meisl, M. Cekada, C. Eisenmenger‐Sittner, T. Schwarz‐Selinger and F. Aumayr, “Transient effects during erosion of WN by deuterium ions studied with the quartz crystal microbalance technique”, Nuclear Instruments and Methods in Physical Research B 382 (2016), pp. 82–85, https://doi.org/10.1016/j.nimb.2016.04.060 .
B.M. Berger, R. Stadlmayr, D. Blöch, E. Gruber, K. Sugiyama, T. Schwarz‐Selinger and F. Aumayr, “Erosion of Fe‐W model system under normal and oblige D ion irradiation”, Nuclear Materials and Energy 12 (2017), https://doi.org/10.1016/j.nme.2017.03.030.
B. M. Berger, P. S. Szabo, R. Stadlmayr and F. Aumayr, “Sputtering measurements using a quartz crystal microbalance as a catcher”, Nuclear Instruments and Methods in Physical Research B (2017), Beam Interactions with Materials and Atoms, 406/Part B, https://doi.org/10.1016/j.nimb.2016.11.039.
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Modeling and theory
Modeling of plasma rotation in tokamaks (completed: June 2016)
A. Martitsch, Institut für Theoretische Physik – Computational Physics, TU Graz; supervisor: W. Kernbichler
The magnetic field of an ideal tokamak without external perturbations has a toroidal symmetry which can be broken due to the finite number of toroidal field coils. Perturbations (e.g. resonant magnetic perturbation – RMP coils for ELM mitigation) lead to a toroidal torque that changes the toroidal rotation velocity of the plasma.
Toroidal plasma rotation has a decisive impact on the operational state of fusion plasmas. Due to technical reasons, small magnetic field perturbations are always present in fusion plasmas. In the frame of this thesis a numerical approach for computing the toroidal torque caused by external magnetic field perturbations was developed. This model was successfully verified against experimental results and may help to actively control fusion plasmas in future devices.
Publications in scientific journals in 2016/2017 (first author):
A.F. Martitsch, S.V. Kasilov, W. Kernbichler, G. Kapper, C.G. Albert, M.F. Heyn, H.M. Smith, E. Strumberger, S. Fietz, W. Suttrop, M. Landreman, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Effect of 3D magnetic perturbations on the plasma rotation in ASDEX Upgrade”, Plasma Physics and Controlled Fusion 58 (2016), https://doi.org/10.1088/0741‐3335/58/7/074007.
The Hamilitonian approach to resonant transport regimes in tokamak plasmas with non‐axisymmetric perturbations (completed: June 2017)
C. Albert, Institut für Theoretische Physik – Computational Physics, TU Graz; Supervisor: W. Kernbichler
The non‐resonant part of non‐axisymmetric perturbations of the magnetic field in tokamaks such as ripple fields, error fields and RMPs introduced for ELM control cause a torque linked to non‐ambipolar transport (neoclassical toroidal viscosity ‐ NTV). In this thesis, the torque from resonant transport regimes for the quasilinear (e.g. superbanana plateau) and non‐linear (e.g. superbanana) limit as well as the transition region between them were evaluated with a Hamiltonian approach.
Results from the implementation of this approach in the code NEO‐RT were validated against runs from the drift‐kinetic codes NEO‐2 and SFINCS at low collisionalities. The importance of the magnetic shear term (which is absent in the standard local neoclassical model) in the magnetic drift frequency and a significant effect of the magnetic drift on drift‐orbit resonances were demonstrated.
Publications in scientific journals in 2016/2017 (first author):
C.G. Albert, M.F. Heyn, S.V. Kasilov, W. Kernbichler and A.F. Martitsch, “Kinetic modeling of 3D equilibria in a tokamak”, Journal of Physics Conference Series 775/1 (2016), http://iopscience.iop.org/article/10.1088/1742‐6596/775/1/012001.
C. Albert, M.F. Heyn, G. Kapper, S.V. Kasilov, W. Kernbichler and A. F. Martitsch,“Evaluation of toroidal torque by non‐resonant magnetic perturbations in tokamaks for resonant transport regimes using a Hamiltonian approach”, Physics of Plasmas 23/8 (2016), https://doi.org/10.1063/1.4961084.
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Full‐F gyro‐fluid modelling of the tokamak edge and scrape‐off layer (completed: March 2017)
M. Held, Institut für Ionenphysik und Angewandte Physik, UIBK; Supervisor: A. Kendl
The first numerical study of this thesis exploited a two dimensional thermal model in a simple slab magnetic field geometry for analyzing the influence of temperature dynamics and dynamic finite Larmor radius (FLR) effects on the interchange motion of SOL blobs.
The second numerical study reproduced drift wave and zonal flow dynamics, using the two‐dimensional ordinary and modified Hasegawa‐Wakatani model. In the next step SOL physics was added to study the interplay between drift waves, zonal flows, interchange dynamics and ion temperature effects around the separatrix.
The last part of this thesis focused on interchange mode blow‐out in a realistic field geometry, showing the typical ballooning of the interchange mode and parallel aligned filaments. Plasma filaments determine the pressure profile in the tokamak SOL and the related particle and heat transport at first wall and divertor. Control and understanding of this transport is of crucial importance for the success of nuclear fusion devices, taking into account the limits of first‐wall materials. Numerical simulations performed in the framework of this thesis have shown that finite ion temperature leads to very compact structures of filaments and significantly enhances zonal flows.
Publications in scientific journals in 2016/2017 (first author):
M. Held, M. Wiesenberger, J. Madsen and A. Kendl, ”The influence of temperature dynamics and dynamic finite ion Larmor radius effects on seeded high amplitude plasma blobs”, Nuclear Fusion 56/12 (2016), https://arxiv.org/abs/1602.04999
Multi‐species gyrofluid tokamak turbulence
O. Meyer, Institut für Ionenphysik und Angewandte Physik, UIBK Innsbruck; Supervisor: A. Kendl
A commercial fusion plasma consists of deuterium‐tritium blend, which is heavier than pure hydrogen or deuterium discharges. Many previous results on plasma turbulence in the plasma edge of tokamaks were obtained with “lighter” plasma mixtures.
Heavy hydrogen isotope plasmas show slower outward filament propagation and thus improved confinement properties compared to light isotope plasmas, regardless of collisionality regimes. Similarly, filaments in fully ionized helium move more slowly than in deuterium. Different mass effects on the filament inertia through polarization, finite Larmor radius, and parallel dynamics were identified and isotopic mass effects on seeded (low amplitude) blob filaments in the tokamak SOL were analyzed by means of a delta‐f
gyrofluid model.
Publications in scientific Journals in 2016/2017 (first author):
O.H.H. Meyer and A. Kendl, “Isotope effect on gyrofluid edge turbulence and zonal flows”, Plasma Physics and Controlled Fusion 58/11 (2016), https://doi.org/10.1088/0741‐3335/58/11/115008.
O.H.H. Meyer and A. Kendl, “Isotope effect on filament dynamics in fusion edge plasmas”, Plasma Physics and Controlled Fusion 59, 065001 (2017), https://doi.org/10.1088/1361‐6587/aa6947
O.H.H. Meyer and A. Kendl, “Isotope effect on blob statistics in gyrofluid simulations of scrape‐off layer turbulence”, Nuclear Fusion 57, 126066 (2017), https://arxiv.org/abs/1705.10641
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Power Plant Physics and Technology
Materials development
Mechanical properties of fusion‐relevant materials
V. Nikolic, Erich‐Schmid Institut für Materialwissenschaft at ÖAW; Supervisor: R. Pippan
Tungsten (W) and tungsten‐based materials are considered as top candidates for fusion applications due to their supreme high temperature properties. Major drawbacks, however, are their low ductility at room temperature and their high ductile‐to‐brittle transition temperature (DBTT). In order to overcome these difficulties, various strategies are explored to enhance the ductility of tungsten. A special focus of this work is on the influence of the microstructure and microstructural changes on the material’s behaviour.
The successful application of W for future fusion devices will be determined by both a decrease of the DBTT and an increase of ductility and fracture toughness. The extreme environment in a fusion reactor poses stringent criteria for the choice of materials, but also paves the way to new developments such as tungsten foil laminates and tungsten wires. The investigation of the mechanical properties of such elements is a major focus of this thesis.
Publications in scientific journals in 2016/2017 (first author):
V. Nikolic, S. Wurster, D. Firneis and R. Pippan, “Improved fracture behavior and microstructural characterization of thin tungsten foils”, Nuclear Materials and Energy 9 (2016), pp.181‐188, https://doi.org/10.1016/j.nme.2016.06.003.
Magnets – High‐Temperature Superconductors
Radiation robustness of superconductors in view of application in fusion devices
D. Fischer, Atominstitut, TU Wien; Supervisor: M. Eisterer
This thesis investigates the impact of neutron irradiation on the ability of high‐temperature superconductors to maintain loss‐free current transport. In the course of this work, a physical model describing the behaviour of superconductors after neutron irradiation is developed.
In a tokamak, ultra‐strong magnetic fields are generated by huge electric currents running through superconducting magnetic coils. The fusion reaction produces helium and a neutron. Although the tiles in the plasma chamber and the radiation shields stop most of the neutrons, a small but relevant fraction hits the superconducting magnet coils and changes the microstructure and physical characteristics of the material. Up to a certain point, the superconductors (SC) improve their ability to sustain dissipation‐free current. Continuing exposure to radiation, however, leads to a reduction of the critical current and to the loss of superconductivity in the worst case.
Publications in scientific journals in 2016/2017 (first author):
D.X. Fischer, R Prokopec, J Emhofer and M. Eisterer, “The effect of fast neutron irradiation on the superconducting properties of REBCO coated conductors with and without artificial pinning centers”, submitted to Superconductor Science and Technology.
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4. PUBLICATIONS
Erich‐Schmid Institute of Materials Science at ÖAW
Conference contribution
V. Nikolic, M. Pfeifenberger, A. Hohenwarter and R. Pippan, “Fracture toughness evaluation and microstructural characterization of drawn tungsten wires”, 18th International Conference on Fusion Reactor Materials (ICFRM‐18), Aomori, Japan, 5 November 2017.
Article in scientific journal
V. Nikolic, S. Wurster, D. Firneis and R. Pippan, “Improved fracture behavior and microstructural characterization of thin tungsten foils”, Nuclear Materials and Energy 9 (2016), pp.181‐188, https://doi.org/10.1016/j.nme.2016.06.003.
Research Studio Salzburg
Conference contributions
H. Cabal, Y. Lechón, Y, F. Gracceva, M. Biberacher, D. Ward, C. Bustreo, D. Dongiovanni and P.E. Grohnheit, “Exploration of fusion power penetration under different global energy scenarios using the EFDA Times energy optimization model”, 26th IAEA Fusion Energy Conference, Kyoto, Japan, 17‐22 October 2016.
H. Cabal, Y. Lechón, F. Gracceva, C. Bustreo, M. Biberacher, D. Dongiovanni, P.E. Grohnheit, S. Fietz and R. Kembledon, “Meeting the new environmental targets with fusion power”, 27th IEEE Symposium On Fusion Engineering, Shanghai, China, 4‐8 June 2017. Technische Universität Graz/Institut für Theoretische Physik – Computational Physics
Conference contributions
2016
C.G. Albert, M.F. Heyn, G. Kapper, S.V. Kasilov, W.Kernbichler, A.F. Martitsch and the EUROfusion MST1 Team, “Hamiltonian approach for evaluation of toroidal torque from finite amplitude non‐axisymmetric perturbations of a tokamak magnetic field in resonant transport regimes”, 43rd European Physical Society Conference on Plasma Physics, Leuven, Belgium, 4‐8 July 2016.
C.G. Albert, M.F. Heyn, S.V. Kasilov, G. Kapper, W.Kernbichler and A.F. Martitsch, “Non‐local quasilinear modelling of the neoclassical toroidal viscosity in tokamaks”, International Conference and School on Plasma Physics and Controlled Fusion, Kharkov, Ukraine, 12 September 2016.
A.F. Martitsch, G. Kapper, S.V. Kasilov, W. Kernbichler, C.G. Albert and M.F. Heyn, “Modeling of the neoclassical toroidal viscous torque in tokamak plasmas”, International Conference and School on Plasma Physics and Controlled Fusion, Kharkov, Ukraine, 12 September 2016.
2017
C.G. Albert, M.F. Heyn, S.V. Kasilov, W. Kernbichler and A. F. Martitsch, “Finite orbit width effects on resonant transport regimes of neoclassical toroidal viscous torque within the Hamiltonian approach”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017
C.G. Albert, M.F. Heyn, S.V. Kasilov, W.Kernbichler, A.F. Martitsch and A.M. Runov, “Modeling of perturbed 3D equilibria using preconditioned iterations”, 21st International Stellarator‐Heliotron Workshop (ISHW2017), 2‐6 October 2017, Kyoto, Japan.
A.F. Martitsch, C.G. Albert, G. Kapper, S.V. Karilov and W. Kernbichler, ”Modeling of the neoclassical toroidal viscous torque in tokamak plasmas with multiple species”, 21st International Stellarator‐Heliotron Workshop ISHW2017), 2‐6 October 2017, Kyoto, Japan.
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W. Kernbichler, G. Kapper, S.V. Kasilov, A.F. Martitsch and N.B. Marushchenko, “Studies of the distribution function computed by NEO‐2 using a fully relativistic Coulomb collision model and its application to ECCD in Wendelstein 7‐X”, 21st International Stellarator‐Heliotron Workshop ISHW2017), 2‐6 October 2017, Kyoto, Japan. Articles in scientific journals
2016
C.G. Albert, M.F. Heyn, S.V. Kasilov, W. Kernbichler and A.F. Martitsch, “Kinetic modeling of 3D equilibria in a tokamak”, Journal of Physics: Conference Series 775/1 (2016), http://iopscience.iop.org/article/10.1088/1742‐6596/775/1/012001.
C. Albert, M.F. Heyn, G. Kapper, S.V. Kasilov, W. Kernbichler and A. F. Martitsch,“Evaluation of toroidal torque by non‐resonant magnetic perturbations in tokamaks for resonant transport regimes using a Hamiltonian approach”, Physics of Plasmas 23/8 (2016), https://doi.org/10.1063/1.4961084.
G. Kapper, S.V. Kasilov, W. Kernbichler, A. Martitsch, M. Heyn, N.B. Marushchenko and Y. Turkin, “Electron cyclotron current drive simulations for finite collisionality plasmas in Wendelstein 7‐X using the full linearized collision model”, Physics of Plasmas 23/11 (2016), https://doi.org/10.1063/1.4968234.
W. Kernbichler, V. Kasilov, G. Kapper, A.F. Martitsch, V. Nemov, C. Albert and M.F. Heyn, “Solution of drift kinetic equation in stellarators and tokamaks with broken symmetry using the code NEO‐2”, Plasma Physics and Controlled Fusion 58/10 (2016), https://doi.org/10.1088/0741‐3335/58/10/104001.
A.F. Martitsch, S.V. Kasilov, W. Kernbichler, G. Kapper, C.G. Albert, M.F. Heyn, H.M. Smith, E. Strumberger, S. Fietz, W. Suttrop, M. Landreman, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Effect of 3D magnetic perturbations on the plasma rotation in ASDEX Upgrade”, Plasma Physics and Controlled Fusion 58 (2016), https://doi.org/10.1088/0741‐3335/58/7/074007.
Technische Universität Wien / Atominstitut
Conference contributions
2016
M. Eisterer, “Angular dependence of the critical current density in coated conductors with an isotropic defect structure”, IEEE Coated Conductors for Applications, Aspen, USA, 11‐14 September 2016.
D.X. Fischer, R. Prokopec and M. Eisterer, “Effects of neutron irradiation on the critical currents of various commercially available coated conductor tapes”, IEEE Coated Conductors for Applications 2016, Aspen, USA, 11 September 2016.
M. Eisterer, “Peaks in the angular dependence of the critical current density in coated conductors resulting from non‐correlated pinning”, Applied Superconductivity Conference, Denver, USA, 4‐9 September 2016.
2017
F. Koechl, A. Loarte, E. de la Luna, I. Nunes, V. Parail, C. Reux, F.G. Rimini, M. Romanelli and JET Contributors, “W transport and accumulation control during the H‐L transition of JET H‐mode discharges and implications for ITER”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
D.X. Fischer, R. Prokopec and M. Eisterer, “Influence of artificial pinning centers on the radiation resistance of coated conductors”, 13th European Conference on Applied Superconductivity (EUCAS), Geneva, Switzerland, 17‐21 September 2017.
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Articles in scientific journals
S. Wiesen, F. Koechl, P. Belo, V. Kotov, A. Loarte, V. Parail, G. Corrigan, L. Garzotti and D. Harting, “Control of particle and power exhaust in pellet fuelled ITER DT scenarios employing integrated models”, Nuclear Fusion 57 (2017), https://doi.org/10.1088/1741‐4326/aa6ecc
D.X. Fischer, R Prokopec, J Emhofer and M. Eisterer, “The effect of fast neutron irradiation on the superconducting properties of REBCO coated conductors with and without artificial pinning centers”, submitted to Superconductor Science and Technology. Technische Universität Wien / Institut für Angewandte Physik
Conference contributions
2016
B.M. Berger, R. Stadlmayr, D. Blöch, K. Sugiyama, T. Schwarz‐Selinger and F. Aumayr, “Erosion of Fe‐W model system under deuterium ion impact“, 27th International Conference on Atomic Collisions in Solids (ICACS‐27), Lanzhou, China, 24‐29 July 2016.
F.M. Laggner, E. Wolfrum, F. Mink, M. Cavedon, M. G. Dunne, P. Manz, G. Birkenmeier, R. Fischer, M. Maraschek, E. Viezzer, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Inter‐ELM pedestal evolution: high frequency magnetic fluctuations correlated with the clamping of the pressure gradient, 43rd European Physical Society Conference on Plasma Physics, Leuven, Belgium, 4‐8 July 2016.
F.M. Laggner, “Pedestal shape, stability and inter‐ELM evolution for different main ion species in ASDEX Upgrade”, 58th Annual Meeting of the APS Division of Plasma Physics, San Jose, California, 31 October – 4 November 2016.
M. Willensdorfer, W. Suttrop, A. Kirk, D. Brida, M. Cavedon, I. Classen, S. Denk, M. Dunne, S. Fietz, R. Fischer, F.M. Laggner, Y.Q. Liu, T. Odstrcil, F. Orain, D.A. Ryan, E. Strumberger, B. Vanovac, E. Viezzer, H. Zohm, I.C. Luhmann, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Plasma response of magnetic perturbations at the edge: Comparisons between measurements and 3D MHD models”, 26th IAEA Fusion Energy Conference, Kyoto, Japan, 17‐22 October 2016.
2017
R. Stadlmayr, B. Berger, D. Blöch, D. Mayer, B. Stechauner, M. Oberkofler, T. Schwarz‐Selinger and F. Aumayr, “Influence of surface structural modifications on the sputtering yield of iron”, 16th International Conference on Plasma‐Facing Materials and Components for Fusion Applications, Neuss/Düsseldorf, Germany, 15‐19 May 2017.
F. Laggner, F. Mink, E. Wolfrum, T. Eich, M. Bernert, G. Birkenmeier, G. Conway, T. Happel, C. Honoré, Ö. Gürcan, P. Manz, A. Medvedeva, U. Stroth, ASDEX Upgrade team and the EUROfusion MST1 Team, “Inter‐ELM fluctuations and flows and their evolution when approaching the density limit in ASDEX Upgrade”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
D. Tskhakaya, S. Brezinsek, D. Borodin, J. Romazanov, R. Ding, A. Eksaeva and Ch. Linsmeier, “Modelling of plasma‐wall interaction and impurity transport in fusion devices and prompt deposition of tungsten as application”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
A. Kirschner, D. Tskhakaya, S. Brezinsek, D. Borodin, J. Romazanov, B. Ding, A. Eksaeva and C. Linsmeier“, ”Modelling of plasma‐wall interaction and impurity transport in fusion devices and prompt deposition of tungsten as application”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
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G.F. Harrer, E. Wolfrum, J. Stober, O. Sauter, P. Lang , G. Birkenmeier, B. Kurzan, R. Fischer, H. Meyer, F.M. Laggner, F. Aumayr, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Dependence of small ELMs on plasma parameters”, 16th International Workshop on H‐mode Physics and Transport Barriers, St Petersburg, Russia, 13‐15 September 2017.
P. Szabo, C. Cupac, D. Blöch, D. Mayer, B. Stechauner, M. Oberkofler, T. Schwarz‐Selinger, A. Mutzke and F. Aumayr, “Consequence of surface morphology modifications on the sputtering yield of iron”, 22nd Intern. Workshop on Inelastic Ion‐Surface Collisions, Dresden, Germany, 17‐22 September 2017.
R. Stadlmayr, P.S. Szabo, B.M. Berger, C. Cupak, R. Chiba, D. Bloch, D. Mayer, B. Stechauner, M. Sauer, A. Foelske‐Schmitz, M. Oberkofler, T. Schwarz‐Selinger, A. Mutzke, and F. Aumayr, “Fluence dependent changes of surface morphology and sputtering yield of iron: comparison of experiments with SDTrimSP‐2D”, 22nd International Workshop on Inelastic Ion‐Surface Collisions, Dresden, Germany, 17‐22 September 2017.
R. Stadlmayr, B.M. Berger, P.S. Szabo, C. Cupak, R. Chiba, D. Blöch, D. Mayer, B. Stechauner, M. Oberkofler, T. Schwarz‐Selinger, A. Mutzke and F. Aumayr, “Consequence of surface morphology modifications on the sputtering yield of iron”, 22nd International Workshop on Inelastic Ion‐Surface Collisions, Dresden, Germany, 17‐22 September 2017.
Articles in scientific journals
2016
B.M. Berger, R. Stadlmayr, G. Meisl, M. Cekada, C. Eisenmenger‐Sittner, T. Schwarz‐Selinger and F. Aumayr, “Transient effects during erosion of WN by deuterium ions studied with the quartz crystal microbalance technique”, Nuclear Instruments and Methods in Physical Research B 382 (2016), pp. 82–85, https://doi.org/10.1016/j.nimb.2016.04.060 .
F.M. Laggner, E. Wolfrum, M. Cavedon, F. Mink, E. Viezzer, M.G. Dunne, P. Manz, H. Doerk, G. Birkenmeier, R. Fischer, S. Fietz, M. Maraschek, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “High frequency magnetic fluctuations correlated with the inter‐ELM pedestal evolution in ASDEX Upgrade”, Plasma Phys. Control. Fusion 58 (2016), https://doi.org/10.1088/0741‐3335/58/6/065005 .
D. Tskhakaya, “Kinetic modelling of the plasma recombination”, Contributions to Plasma Physics, 56 (2016), doi/10.1002/ctpp.201611004/abstract.
M. Willensdorfer, S.S. Denk, E. Strumberger, W. Suttrop, B. Vanovac, D. Brida, M. Cavedon, I. Classen, M. Dunne, S. Fietz, R. Fischer, A. Kirk, F.M. Laggner, Y. Q. Liu, T. Odstrcil, D.A. Ryan, E. Viezzer, H. Zohm, I.C. Luhmann, the ASDEX Upgrade Team and the EUROfusion MST1 Team, “Plasma response measurements of magnetic perturbations using electron cyclotron emission and comparison to 3D ideal MHD equilibrium”, Plasma Physics and Controlled Fusion, 58/11 (2016), https://doi.org/10.1088/0741‐3335/58/11/114004.
2017
B.M. Berger, R. Stadlmayr, D. Blöch, E. Gruber, K. Sugiyama, T. Schwarz‐Selinger and F. Aumayr, “Erosion of Fe‐W model system under normal and oblige D ion irradiation”, Nuclear Materials and Energy 12 (2017), https://doi.org/10.1016/j.nme.2017.03.030 .
B.M. Berger, P.S. Szabo, R. Stadlmayr and F. Aumayr, ”Sputtering measurements using a quartz crystal microbalance as a catcher“, Nuclear Instruments and Methods in Physics Research B (2017), Beam Interactions with Materials and Atoms, 406/ B, https://doi.org/10.1016/j.nimb.2016.11.03 .
F.M. Laggner, E. Wolfrum, M. Cavedon, F. Mink, M. Bernert, M. G. Dunne, P. A. Schneider, A. Kappatou, G. Birkenmeier, R. Fischer, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Pedestal structure and inter‐ELM evolution for different main ion species in ASDEX Upgrade”, Physics of Plasmas 24 (2017), https://doi.org/10.1063/1.4977461 .
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F.M. Laggner, S. Keerl, J. Gnilsen, E. Wolfrum, M. Bernert, D. Carralero, L. Guimarais, V. Nikolaeva, S. Potzel, M. Cavedon, F. Mink, M.G. Dunne, G. Birkenmeier, R. Fischer, E. Viezzer, M. Willensdorfer, M. Wischmeier, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Divertor, scrape‐off layer and pedestal particle dynamics in the ELM cycle on ASDEX Upgrade”, Plasma Physics and Controlled fusion 60/2 (2017), https://doi.org/10.1088/1361‐6587/aa90bf.
F.M. Laggner, E. Wolfrum, M. Cavedon, M.G. Dunne, G. Birkenmeier, R. Fischer, M. Willensdorfer, F. Aumayr, the EUROfusion MST1 Team and the ASDEX Upgrade Team, “Plasma shaping and its impact on the pedestal of ASDEX Upgrade: Edge stability and inter‐ELM dynamics at varied triangularity”, submitted to Nuclear Fusion. Universität Innsbruck / Institut für Ionenphysik und Angewandte Physik
Conference contributions
2016
C. Ionita, S. Costea, B.S. Schneider, J. Kovačič, V. Naulin, J.J. Rasmussen, N. Vianello, M. Spolaore, T. Gyergyek and R. Schrittwieser, “Development of electric probes for improved diagnostics characterizing filamentary transport in mid‐size tokamaks”, 27th Symposium on Plasma Physics and Technology, Prague, Czech Republic, 20‐23 June 2016.
S. Costea, B. Fonda, J. Kovacic, T. Gyergyek, B. S. Schneider, R. Schrittwieser and C. Ionita, “Bunker probe for direct measurements of the plasma potential less sensitive to deviations of its alignment with the magnetic field”, 43rd European Physical Society Conference on Plasma Physics, Leuven, Belgium, 4‐8 July 2016.
S. Costea, D. Carralero, J. Madsen, N. Vianello, V. Naulin, A. H. Nielsen, J. J. Rasmussen, R. Schrittwieser, C. Ionita, M. Spolaore, J. Kovacic, the ASDEX Upgrade team and the EUROfusion MST1 Team, “Inter‐ELM filamentary studies during density ‘shoulder’ formation in ASDEX Upgrade”, 43rd European Physical Society Conference on Plasma Physics, Leuven, Belgium, 4‐8 July 2016.
M. Held, M. Wiesenberger, J. Madsen and A. Kendl, “Thermal effects on seeded finite ion temperature, high amplitude plasma blobs” 43rd European Physical Society Conference on Plasma Physics, Leuven, Belgium, 4‐8 July 2016.
B.S. Schneider, S. Costea, C. Ionita, R. Schrittwieser, V. Naulin, J.J. Rasmussen, N. Vianello, M. Spolaore, J. Kovacic, T. Gyergyek and R. Stärz, “Advanced probe for transport measurements in Medium‐Size Tokamaks”, 29th Symposium on Fusion Technology (SOFT), 5‐9 September 2016.
M. Probst, I. Sukuba, J. Urban, A. Kaiser, T. Maihom, J. Limtrakul, K. Hermansson, D. Borodin and S. Huber, “Total electron‐impact ionization cross sections of molecules and ions in fusion plasma”, 26th IAEA Fusion Energy Conference, Kyoto, Japan, 17‐22 October 2016.
D. Borodin, S. Brezinsek, I. Borodkina, M. Probst, S. W. Lisgo, R. A. Pitts, M. Kocan, C. Björkas, A. Kirschner, J. Romazanov, J. Miettunen, M. Groth and C. Linsmeier, “ERO modelling of Be erosion in JET and extrapolation of the data for ITER”, 26th IAEA Fusion Energy Conference, Kyoto, Japan, 17‐22 October 2016.
2017
S. Costea, D. Tskhakaya, J. Kovacic, T. Gyergyek, R. Schrittwieser, C. Ionita and B.S. Schneider, “Particle‐in‐Cell simulation of parallel blob dynamics in near scrape‐off layer plasma of medium‐size tokamak”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
B.S. Schneider, C.K. Tsui, N. Vianello, M. Spolaore, J. Boedo, Naulin, J.J. Rasmussen, R. Staerz, J. Kovacic T. Gyergyek, S. Costea, C. Ionita, R. Schrittwieser and K. Popov, “Multi‐diagnostic probe head for near‐wall electric and magnetic measurements in medium‐size tokamaks”, 44th European Physical Society Conference on Plasma Physics, Belfast, Northern Ireland, 26‐30 June 2017.
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C. Ionita, B.S. Schneider, S. Costea, J. Kovacic, M. Spolaore, V. Naulin, N. Vianello, J.J. Rasmussen, T. Gyergyek, R. Staerz and R. Schrittwieser, “Recent developments in probe diagnostics”, XXXIII International Conference on Phenomena in Ionized Gases (ICPIG), Estoril/Lisbon, Portugal, 9‐14 July 2017.
S. Costea, J. Kovacic, D. Tskhakaya, T. Gyergyek, K. Popov, M. Dimitrova, B. Schneider, C. Ionita, R. Schrittwieser, Kinetic simulation of parallel particle and momentum transport of blobs using a particle‐in‐cell code”, 26th International conference on Nuclear energy for New Europe (NENE 2017); Bled, Slovenia, 11‐14 September 2017.
Articles in scientific journals
2016
S. Costea, B. Fonda, J. Kovacic, T. Gyergyek, B.S. Schneider, R. Schrittwieser and C. Ionita, “Bunker probe: a plasma potential probe almost insensitive to its orientation with the magnetic field”, Review of Scientific Instruments 87 (2016), https://doi.org/10.1063/1.4951688.
M. Gyoeroek, A. Kaiser, I. Sukuba, J. Urban, K. Hermansson and M. Probst, “Surface binding energies of beryllium/tungsten alloys”, Journal of Nuclear Materials 472 (2016), https://doi.org/10.1016/j.jnucmat.2016.02.002.
M. Held, M. Wiesenberger, J. Madsen and A. Kendl, “The influence of temperature dynamics and dynamic finite ion Larmor radius effects on seeded high amplitude plasma blobs”, Nuclear Fusion 56 (2016), https://doi.org/10.1088/0029‐5515/56/12/126005.
O.H.H. Meyer and A. Kendl, “Isotope effect on gyrofluid edge turbulence and zonal flows”, Plasma Physics and Controlled Fusion 58/11 (2016), https://doi.org/10.1088/0741‐3335/58/11/115008.
A. Stegmeir, O. Maj, D. Coster, K. Lackner M. Held and M. Wiesenberger, “Advances in the flux‐coordinate independent approach”, Computer Physics Communications 213 (2017), https://doi.org/10.1016/j.cpc.2016.12.014.
I. Sukuba, A. Kaiser, S. Huber, J. Urban and M. Probst, “Electron‐impact cross sections of beryylium‐tungsten clusters”, European Physical Journal D 70:11 (2016), https://doi.org/10.1140/epjd/e2015‐60583‐7
2017
O.H. Meyer and A. Kendl, “Isotope effect on filament dynamics in fusion edge plasmas”, Plasma Physics and Controlled Fusion 59 (2017), https://doi.org/10.1088/1361‐6587/aa6947.
O.H. Meyer and A. Kendl, “Isotope effect on blob statistics in gyrofluid simulations of scrape‐off layer turbulence”, Nuclear Fusion 57 (2017), https://arxiv.org/abs/1705.10641.
J. Peer, A. Kendl, T.T. Ribeiro and B.D. Scott; “Gyrofluid computation of magnetic perturbation effects on turbulence and edge localized bursts”, Nuclear Fusion 57/8 (2017), https://doi.org/10.1088/1741‐4326/aa777f.
N. Vianello, C. Tsui, C. Theiler, S. Allan, J. Boedo, B. Labit, H. Reimerdes, K. Verhaegh, W. Vijvers, N. Walkden, S. Costea, J. Kovacic, C. Ionita, V. Naulin, A. H. Nielsen, J. J. Rasmussen, B. Schneider, R. Schrittwieser, M. Spolaore, D. Carralero, J. Madsen, B. Lipschultz and F. Militello, “Modification of SOL profiles and fluctuations with line‐average density and divertor flux expansion in TCV”, Nuclear Fusion 57 (2017), https://doi.org/10.1088/1741‐4326/aa7db3.
M. Wiesenberger, M. Held and L. Einkemmer, “Streamline integration as a method for two‐dimensional elliptic grid generation”, Journal of Computational Physics 340 (2017), https://doi.org/10.1016/j.jcp.2017.03.056.
Universität Innsbruck / Institut für Theoretische Physik
Conference contributions
26
2016 R. Kwiatkowski, G. Boltruczyk, M. Gosk, S. Korolczuk, S. Mianowski, A. Szydlowski, I. Zychor, V. Braic, R. Costa Pereira, T. Craciunescu, D. Croft, M. Curuia, A. Fernandes, V. Goloborodko, G. Gorini, V. Kiptily, I. Lengar, J. Naish, R. Naish, M. Nocente, K. Schoepf, B. Santos, S. Soare, M. Tardocchi, V. Yavorskij and V.L. Zoita, “CeBr3‐based detector for gamma spectrometer upgrade at JET”, 29th Symposium on Fusion Technology (SOFT), Prague, Czech Republic, 5‐9 September 2016.
M. Curula, T. Craciunescu, S. Soare, V.L. Zoita, V. Braic, D. Croft, A. Fernandes, J. Figueiredo, V. Goloborodko, G. Gorini, S. Griph, V. Kiptily, I. Lengar, S. Mianowski, J. Naish, R. Naish, M. Nocente, R. C. Pereira, V Riccardo, K. Schoepf, B. Santos, M. Tardocchi, V. Yavorskij and I. Zychor, “Upgrade of the tangential gamma‐ray spectrometer beam‐line for JET DT experiments”, 29th Symposium on Fusion Technology (SOFT), Prague, Czech Republic, 5‐9 September 2016.
S. Soare, V.L. Zoita, V. Braic, T. Craciunescu, D. Falie, V. Goloborod’ko, V. Kiptily, I. Lengar, R.C. Pereira, V. Yavorskij, I. Zychor, N. Balshaw, D. Croft, A. Cufar, M. Curuia, A. Fernandes, J. Figueiredo, Y. Krivchenkov, N. Lam, C. Marren, S. Mianowski, V. Riccardo, K. Schoepf, Z. Stancar, and JET Contributors, “Conceptual design of a gamma‐ray monitor for lost alpha particles in JET”, 29th Symposium on Fusion Technology (SOFT), Prague, Czech Republic, 5‐9 September 2016.
2017
S. Soare, V.L. Zoita, V. Braic, T. Craciunescu, D. Falie, V. Goloborod’ko, V. Kiptily, I. Lengar, R.C. Pereira, V. Yavorskij, I. Zychor, N. Balshaw, D. Croft, A. Cufar, M. Curuia, A. Fernandes, J. Figueiredo, Y. Krivchenkov, N. Lam, C. Marren, S. Mianowski, V. Riccardo, K. Schoepf, Z. Stancar, L. Swiderski, V. Thompson and JET contributors, “Lost alpha particle monitor for JET: a conceptual design”, 17th International Conference on Plasma Physics and Applications, Magurele, Bucharest, Romania, 15‐20 June 2017.
Articles in scientific journals
2016
V. Yavorskij, V. Goloborod'ko and K. Schoepf, “Fokker‐Planck model for collisional loss of fast ions in tokamaks”, Nuclear Fusion 56/11 (2016), https://doi.org/10.1088/0029‐5515/56/11/112001.
2017
V. Kiptily, A.E. Shevelev, V. Goloborodko, M. Kocan, E. Veshchev, T. Craciunescu, I. Lengar, K. Schoepf, S. Soare, V. Yavorskij and V.L. Zoita, “Escaping alpha‐particle monitor for burning plasmas”, submitted to Nuclear Fusion.
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AUSTRIAN PARTICIPATION (Fusion@ÖAW)
MANAGEMENT STRUCTURE
EUROFUSION ORGANIGRAM
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AUSTRIAN REPRESENTATIVES IN COMMITTEES RELEVANT FOR FUSION RESEARCH AND
DEVELOPMENT (2016/2017)
Fusion Programme Committee
Dr. Daniel Weselka Federal Ministry of Science, Research and Economy
Univ.Prof.Dr. Friedrich Aumayr (Expert)
Institut für Angewandte Physik/ Technische Universität Wien
EUROFusion General Assembly
Univ.Prof.Dr. Friedrich Aumayr
Institute of Applied Physics/ Technische Universität Wien
FUSECom (EUROfusion Communicators`network) Mag. Monika Fischer Austrian Academy of Sciences
Lätitia Unger, BSc. Austrian Academy of Sciences
Fusion for Energy (F4E) Governing Board
Dr. Daniel Weselka Federal Ministry of Science, Research and Economy
Univ.Prof.Dr. Harald W. Weber Atominstitut / Technische Universität Wien F4E Administration and Management Committee Mag. Monika Fischer Austrian Academy of Sciences
Industrial Liaison Officer
Mag. Birgit Murr
Austrian Federal Economic Chamber
Kommission für die Koordination der Kernfusionsforschung in Österreich (KKKÖ) Chair: Univ.Prof.Dr. Peter Steinhauser (ÖAW)
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ABBREVIATIONS AND ACRONYMS
Fusion experiments
AUG ASDEX Upgrade, facility at IPP Garching
ITER “The way” (under construction at Cadarache, France)
JET
MAST
Joint European Torus, UKAEA, Culham, UK
Mega Amp Spherical Tokamak
TCV Tokamak à Configuration Variable, EPFL, Lausanne, Switzerland
W7‐X Wendelstein 7‐X, IPP Greifswald, Germany
University Institutes and other institutions CCFE Culham Centre for Fusion Energy (United Kingdom)
EPFL École polytechnique fédérale de Lausanne
F4E Fusion for Energy
IPP Institut für Plasmaphysik, Garching (Germany)
ÖAW Österreichische Akademie der Wissenschaft
ÖAW‐ESI Erich‐Schmid Institut für Materialwissenschaft at ÖAW
TU Graz Technische Universität Graz
TU Wien Technische Universität Wien
UIBK Universität Innsbruck
Scientific and technical abbreviations AFM Atomic force microscopy
DBTT Ductile‐to‐brittle‐transition
ELMs Edge localized modes
FLR Finite Larmor radius
NTV Neoclassical toroidal viscosity
PFC Plasma‐facing components
RMP Resonant magnetic perturbations
QCM Quartz crystal microbalance
SOL Scrape‐off layer
W Tungsten
Technical terms
Fluence The total number of particles per unit area with which a material is irradiated
H‐mode regime A high confinement regime develops when a tokamak plasma is heated above a characteristic power threshold, which increases with density, magnetic field and machine size. It is characterized by a sharp temperature gradient near the plasma edge (resulting in an edge “temperature pedestal”). The H‐mode typically doubles the energy
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CONTACT INFORMATION
Österreichische Akademie der Wissenschaften, Fusion@ÖAW Coordination Office Apostelgasse 23 1030 Wien Tel.: +43‐1‐51581‐2675, 2676
Monika Fischer [email protected] Lätitia Unger [email protected] Friedrich Aumayr [email protected]
Erich‐Schmid Institut für Materialwissenschaft der ÖAW Jahnstr. 12, 8700 Leoben Tel.: +43‐3842‐804311
Reinhard Pippan [email protected] Vladica Nikolic [email protected]
Research Studios Austria Forschungsgesellschaft mbH Leopoldskronstraße 30, 5020 Salzburg Tel.: +43 (0) 662 908585 – 221
Markus Biberacher [email protected]
Institut für Theoretische Physik, Technische Universität Graz
Petersgasse 16, 8010 Graz Tel.: +43‐316‐873‐8182
Winfried Kernbichler [email protected] Martin Heyn [email protected]
Atominstitut, Technische Universität Wien Stadionallee 2, 1020 Wien Tel.: +43‐1‐58801‐141552
Michael Eisterer [email protected] Florian Köchl [email protected] Helmut Leeb [email protected]
Institut für Angewandte Physik, Technische Universität Wien Wiedner Hauptstraße 8‐10, 1040 Wien Tel. +43‐1‐58801‐13430
Friedrich Aumayr [email protected] David Tskhakaya [email protected] Tel. +43‐(0)699‐11609766
Institut für Ionenphysik und Angewandte Physik, Universität Innsbruck Technikerstraße 25, 6020 Innsbruck Tel.: +43‐512‐507‐52720, 52730, 52660, 52740 , 52741
Alexander Kendl [email protected] Michael Probst [email protected] Paul Scheier [email protected] Roman Schrittwieser [email protected] Codrina Ionita‐Schrittwieser [email protected]
Institut für Theoretische Physik, Universität Innsbruck Technikerstraße 25, 6020 Innsbruck
Klaus Schöpf [email protected] mobile: +43 (0)650 2829540
Back cover: Image © Fusion@ÖAW