DOCSLIB.ORG

Work Plan Will Be Implemented

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Work Plan Will Be Implemented Version 6 May 2020 DESCRIPTION OF ACTION FOR THE IMPLEMENTATION OF THE FUSION ROADMAP IN 2021-2027 Annex 1 - Part B Chapter 3 Please note that this is a draft version of Chapter 3 of the Grant proposal. It is a further evolved version of the one that has been distributed by the end of 2019 to GA, STAC and EFPW. But it is still being worked at by PMU and the writers group. The present version is mainly attached to the call to give a fair idea what topics are covered by each of the work packages. Page 1 of 143 Version 6 May 2020 Page 2 of 143 Version 6 May 2020 Change Log Reason for change Version Date Original version given to the PMU team 1 23/02/2020 New version after the various subsections have been reworked by PMU 2 03/04/2020 Page 3 of 143 Version 6 May 2020 Participant No. Participant Short name Country 1 (Coordinator) MPG Germany 2 OEAW Austria 3 LPP-ERM-KMS Belgium 4 INRNE Bulgaria 5 RBI Croatia 6 UCY Cyprus 7 IPP.CR Czech Republic 8 DTU Denmark 9 UT Estonia 10 VTT Finland 11 CEA France 12 FZJ Germany 13 KIT Germany 14 NCSRD Greece 15 WIGNER RCP Hungary 16 DCU Ireland 17 ENEA Italy 18 ISSP-UL Latvia 19 LEI Lithuania 20 NWO-I-DIFFER Netherlands 21 IPPLM Poland 22 IST Portugal 23 IAP Romania 24 CU Slovakia 25 JSI Slovenia 26 CIEMAT Spain 27 VR Sweden 28 EPFL Switzerland 29 CCFE United Kingdom 30 KIPT Ukraine Page 4 of 143 Version 6 May 2020 Table of Contents Change Log ........................................................................................................................................................................ 3 3. IMPLEMENTATION ............................................................................................................................... 7 3.1 Overall Implementation of the Programme ....................................................................................................... 7 Campaign oriented implementation .......................................................................................................................... 7 Project orientated implementation ............................................................................................................................ 8 Table 3.1a List of Work Packages ..................................................................................................................... 8 Table 3.1b List of Deliverables ........................................................................................................................... 9 Table 3.1c List of Milestones .............................................................................................................................. 9 Table 3.1d List of Critical Risks & Mitigation Strategy .................................................................................. 9 3.2 Fusion Science ..................................................................................................................................................... 10 01 EU Tokamaks Exploitation and Theory-Simulation-Verification-Validation (WPTE) ........... 10 02 Exploitation of JT-60SA and Theory-Simulation-Verification-Validation (WPSA) ................ 20 03 Exploitation of W7-X and Theory-Simulation-Verification-Validation (WPW7X) .................. 22 04 Advanced Computing (WPAC) ..................................................................................................... 27 05 Plasma Wall Interaction and Exhaust and Theory-Simulation-Verification-Validation (WPPWIE) ...................................................................................................................................... 30 06 Preparation of ITER Operation (WPPrIO) ................................................................................. 37 07 Enabling Research (WPENR) ....................................................................................................... 41 3.3 Fusion Technology .............................................................................................................................................. 43 08 Design-assist Activities (WPDES, directed by the DCT) ............................................................. 44 09 Magnet System (WPMAG) ............................................................................................................ 53 10 Breeding Blanket (WPBB) ............................................................................................................. 57 11 Plant Electrical Systems (WPPES) ............................................................................................... 64 12 Divertor (WPDIV) .......................................................................................................................... 68 13 Heating & Current Drive (WPHCD) ............................................................................................ 77 14 Tritium, Fuelling & Vacuum (WPTFV) ....................................................................................... 82 15 Balance of Plant (WPBOP) ............................................................................................................ 87 16 Diagnostics & Control (WPDC) .................................................................................................... 91 17 Remote Maintenance (WPRM) ..................................................................................................... 94 18 Materials (WPMAT, incl. MAT-TBM collaboration) ............................................................... 102 19 Safety & Environment (WPSAE) ................................................................................................ 107 20 Early Neutron Source (WPENS) ................................................................................................. 110 21 Prospective R&D (WPPRD) ........................................................................................................ 115 22 Socio Economic Studies (WPSES) .............................................................................................. 121 3.4 Communications ............................................................................................................................................... 123 23 Communications (WPCOMM) ................................................................................................... 123 3.5 Training and education .................................................................................................................................... 127 24 Training and Education (WPTRED) .......................................................................................... 127 3.6 Management ..................................................................................................................................................... 131 25 Programme Management Unit (WPPMU) ................................................................................. 131 3.7 Technology Transfer ........................................................................................................................................ 133 26 Technology Transfer (WPTT) ..................................................................................................... 133 3.8 International Collaborations Coordination (INCO) ...................................................................................... 135 Page 5 of 143 Version 6 May 2020 Programmatic context impacting the approach to international collaboration ................................................. 136 High-level guidelines for international collaboration ........................................................................................... 137 Implementation of international collaborations ................................................................................................... 137 Main topics identified for collaboration with the international partners ........................................................... 138 3.9 Industrial Involvement ..................................................................................................................................... 301 Page 6 of 143 Version 6 May 2020 3. IMPLEMENTATION 3.1 Overall Implementation of the Programme The implementation of the activities is broken down into Work Packages (WP) that mirror the structure of the programmatic deliverables. An overview of all WPs in alphabetic order, and their relation to the roadmap missions is given in Fig. 3.1. Acronym Work Package Mission 1 Mission 2 Mission 3 Mission 4 Mission 5 Mission 6 Mission 7 Mission 8 AC Advanced Computing BB Breeding Blankets BoP Balance of Plant COMM Communications DC Diagnostics & Control DES Design Activities DIV Divertor Engineering ENS Early Neutron Source ENR Enabling Research HCD Heating & Current Drive MAG Magnets MAT Materials PES Plant Electrical Systems PRD Prospective Research & Development PrIO Preparation of ITER Operation PWIE Plasma Wall Interaction & Exhaust RM Remote Maintenance SA JT60-SA Exploitation & TSVV SAE Safety and Environment SES Socio-Economic Studies TE Tokamak Exploitation & TSVV TRED Training and Education TFV Tritium Fuelling & Vacuum TT Technology Transfer W7X W7-X Exploitation & TSVV Figure 3.1: Overview of all Work Packages and their relation to the roadmap missions This Chapter outlines the WPs in which the Work Plan will be implemented. For each WP, the top- level management scheme is given along with a description of the deliverables. The dates in brackets for the key deliverables are indicative. The detailed breakdown will be
Load more

Recommended publications
  • Overview of the SPARC Tokamak
    This is a repository copy of Overview of the SPARC tokamak. White Rose Research Online URL for this paper: https://eprints.whiterose.ac.uk/166980/ Version: Published Version Article: Creely, A. J., Greenwald, M. J., Ballinger, S. B. et al. (42 more authors) (2020) Overview of the SPARC tokamak. Journal of Plasma Physics. 865860502. ISSN 0022-3778 https://doi.org/10.1017/S0022377820001257 Reuse This article is distributed under the terms of the Creative Commons Attribution-NonCommercial-NoDerivs (CC BY-NC-ND) licence. This licence only allows you to download this work and share it with others as long as you credit the authors, but you can’t change the article in any way or use it commercially. More information and the full terms of the licence here: https://creativecommons.org/licenses/ Takedown If you consider content in White Rose Research Online to be in breach of UK law, please notify us by emailing [email protected] including the URL of the record and the reason for the withdrawal request. [email protected] https://eprints.whiterose.ac.uk/ J. Plasma Phys. (2020), vol. 86, 865860502 © The Author(s), 2020. 1 Published by Cambridge University Press This is an Open Access article, distributed under the terms of the Creative Commons Attribution-NonCommercial-NoDerivatives licence (http://creativecommons.org/licenses/by-nc-nd/4.0/), which permits non-commercial re-use, distribution, and reproduction in any medium, provided the original work is unaltered and is properly cited. The written permission of Cambridge University Press must be obtained for commercial re-use or in order to create a derivative work.
    [Show full text]
  • Fusion - a Clean Future Research at Culham Centre for Fusion Energy
    Fusion - A clean future Research at Culham Centre for Fusion Energy FUSION REACTION Increasing energy demands, concerns over climate change and limited supplies of fossil fuels mean that we need to find new, cleaner ways of powering the planet. Nuclear fusion – the process that drives the sun – could play a big part in our sustainable energy future. Around the globe, scientists and engineers are working to make fusion a real option for our electricity supply. At the forefront of this research is Culham Centre for Fusion Energy, home to the UK’s fusion programme and to the world’s largest fusion device, JET, which we operate for scientists from over 20 European countries. Why we need fusion energy Energy consumption is expected to grow dramatically over the next fifty years as the world’s population expands and developing countries become more industrialised. The population of the developing world is predicted to expand from seven billion to nearly ten billion by 2050. As a consequence, a large increase in energy demand can be expected, even if energy can be used more efficiently. At the same time, we need to find new ways of producing our energy. Fossil fuels bring atmospheric pollution and the prospect of climate change; Governments are divided over whether to include nuclear fission in their energy portfolios; and renewable sources will not be enough by themselves to meet the demand. Nuclear fusion can be an important long-term energy source, to complement other low-carbon options such as fission, wind, solar and hydro. Fusion power has the potential to provide more than one-third of the world’s electricity by the year 2100, and will have a range of advantages: • No atmospheric pollution.
    [Show full text]
  • Wendelstein 7-X in the European Roadmap to Fusion Electricity
    Wendelstein 7-X in the European Roadmap to Fusion Electricity Enrique Ascasíbar for the W7-X Team This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the European Union‘s Horizon 2020 research and innovation programme under grant agreement number 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Andreas DINKLAGE | Hungarian Plasma Physics and Fusion Technology Workshop | Tengelic, Hungary | 09. Mar. 2015 | Page 2 Outline 1. Introduction and Motivation:Stellarators in the EU Roadmap 2. Operational Phases of W7-X: OP1.1, OP1.2 3. Aspects of SSO 4. Summary Enrique ASCASIBAR | 8th IAEA TM ‘Steady-State Operation of Magnetic Fusion Devices’ | Nara, Japan | 26.-29. May 2015 | Page 3 Wendelstein 7-X, the Engineers’ View mass: 725 t ECRH heating plasma vessel 254 ports 117 diagnostics ports R = 5.6 m OP1.1: 5.3 MW a = 0.5 m 3 Vplasma= 30 m B ≤ 3 T = 5/6 - 5/4 outer vessel 20 planar SC coils 10 divertor units support structure 50 non-planar SC coils plasma 1st ECPD 14.-17. Apr. 2015 4 Europe and W7-X / W7-X and Europe Introduction and Motivation: Stellarators in the Roadmap http://www.efda.org/wpcms/wp‐content/uploads/2013/01/JG12.356‐web.pdf?5c1bd2 EU Roadmap: Eight Missions: Mission 8 Bring the HELIAS line to maturity Long-term alternative to tokamaks: mitigate risks and enhance synergies: Wendelstein 7-X is an integral part of the European fusion development strategy. Enrique ASCASIBAR | 8th IAEA TM ‘Steady-State Operation of Magnetic Fusion Devices’ | Nara, Japan | 26.-29.
    [Show full text]
  • Analysis of JT-60SA Operational Scenarios DEMO Scenarios G
    PAPER Related content - Modelling of pulsed and steady-state Analysis of JT-60SA operational scenarios DEMO scenarios G. Giruzzi, J.F. Artaud, M. Baruzzo et al. To cite this article: L. Garzotti et al 2018 Nucl. Fusion 58 026029 - Chapter 6: Steady state operation C. Gormezano, A.C.C. Sips, T.C. Luce et al. - 2008 Public Release of the ITPA Confinement Profile Database View the article online for updates and enhancements. C.M. Roach, M. Walters, R.V. Budny et al. Recent citations - Feasibility of a far infrared laser based polarimeter diagnostic system for the JT- 60SA fusion experiment A Boboc et al This content was downloaded from IP address 194.81.223.66 on 19/09/2019 at 12:02 IOP Nuclear Fusion International Atomic Energy Agency Nuclear Fusion Nucl. Fusion Nucl. Fusion 58 (2018) 026029 (13pp) https://doi.org/10.1088/1741-4326/aa9e15 58 Analysis of JT-60SA operational scenarios 2018 L. Garzotti1 , E. Barbato2, J. Garcia3 , N. Hayashi4, I. Voitsekhovitch1, G. Giruzzi3, P. Maget3, M. Romanelli1, S. Saarelma1, R. Stankiewitz5, © 2018 EURATOM M. Yoshida4 and R. Zagórski5 1 NUFUAU CCFE, Culham Science Centre, Abingdon, Oxon, OX14 3DB, United Kingdom 2 Unità Tecnica Fusione, ENEA C. R. Frascati,via E. Fermi 45, 00044 Frascati (Roma), Italy 3 CEA, IRFM, F-13108 Saint Paul Lez Durance, France 026029 4 National Institutes for Quantum and Radiological Science and Technology, Naka, Ibaraki 311-0193, Japan 5 Institute of Plasma Physics and Laser Microfusion, Hery 23, 01-497 Warsaw, Poland L. Garzotti et al E-mail: [email protected] Scenarios JT-60SA Received 7 June 2017, revised 17 November 2017 Accepted for publication 29 November 2017 Published 5 January 2018 Printed in the UK Abstract NF Reference scenarios for the JT-60SA tokamak have been simulated with one-dimensional transport codes to assess the stationary state of the flat-top phase and provide a profile database for further physics studies (e.g.
    [Show full text]
  • Nuclear Fusion As a Solution to Energy Needs Gerencia De Riesgos Y Seguros
    Nuclear Fusion as a Solution to Energy Needs gerencia de riesgos y seguros Nuclear Fusion as a Solution to Energy Needs Society needs new options to sustainably meet the population’s growing demand for energy. With this objective, researchers worldwide have been working for decades to create fusion power, which is a massive, sustainable source of energy that is a veritable scientific and technological challenge. However, industrial production and commercialization of this power source may not be achieved until the second half of this century. “The search for sources of energy goes back to the dawn of the human race,” acknowledges Carlos Hidalgo, head of the Experimental Physics Division at the National Fusion Laboratory at CIEMAT (Center for Energy, Environmental, and Technological Research). The current problem is that people’s needs have multiplied by a factor of 100 throughout history. And advances in this field of research have caused radical changes in our society. In fact, experts estimate that humans’ demand for primary energy will have grown 25% by 2040 and will be close to doubling by the end of the century. These predicted scenarios will require an investment of more than 2 trillion dollars per year in new energy sources according to the World Energy Outlook 2018, published by the International Energy Agency. If this amount is not invested and a viable solution is not found, it could lead to a large-scale energy crisis. Against this backdrop, fusion power stands out as the principal energy source of tomorrow: clean, safe, and, in theory, limitless. Yet, Hidalgo urges caution as “the need for new strategies to generate, convert, and store power represents a colossal challenge,” while the dynamics of energy markets are increasingly impacted by the exponential growth of the population and demand.
    [Show full text]
  • Magnetic Field Coils Misaligments on the COMPASS-U Tokamak
    Magnetic field coils misaligments on the COMPASS-U tokamak Kripner, L.1), 2), Krbec, J.1), Zelda, J.1), Hacek, P.1), Markovic, T.1), 2), Ficker, O.1), 3), Vondracek, P.1), COMPASS team4) 1)Institute of Plasma Physics of the CAS, Za Slovankou 3, Prague, Czech Republic 2)Faculty of Mathematics and Physics, Charles University, Prague, Czech Republic 3)Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, Prague, Czech Republic 4) See author list of "M. Hron et. al 2021 'Overview of the COMPASS results' submitted to Nucl. Fusion" Introduction Toroidal magnetic ripple ● The finite magnetic coil winding, and assembly mialigments introduce toroidal asymmetry in magnetic field . ● The toroidal asymmetry of the tokamak magnetic field can lead to unwanted MHD instabilities and decrease plasma confinement. ● Magnetic field is calculated using Biot-Savart law with realistic winding Midplane cut of |B| of toroidal field (TF) coils. ● The effects of toroidal coils misalignments are analysed using Monte [Scott, S. D. et al., J. Plasma Phys. 100, (2020).] Carlo calculations. ● Each deviation type is explored separately. Toroidal field configuration & z y Sliding x displacement joint Distribution of current in the TF coils during the discharge Upper limb Core Midplane bolted joint Ripple with displacement Bottom bolted joint Lower limb Deviation 3 σ arrows indicates worst case Radial shift [+-0.5,+-1, scenarios (shift z) +-1.5, +-2.0] mm Vertical shift [+-0.5,+-1, (shift z) +-1.5, +-2.0] mm Normal shift [+-0.05,+-0.2,
    [Show full text]
  • An Unreal Reality Pushes Fusion Science Jet – the Most Successful Performance in Years How to Tame Plasma Turbulence
    FUSION IN EUROPE NEWS & VIEWS ON THE PROGRESS OF FUSION RESEARCH AN UNREAL REALITY PUSHES FUSION SCIENCE JET – THE MOST SUCCESSFUL PERFORMANCE IN YEARS HOW TO TAME PLASMA TURBULENCE 4 2016 FUSION IN EUROPE 4 2016 Contents Delphine Keller from EURO­ fusion’s French Research Unit Moving Forward CEA is dressed for a jump into the virtual fusion world. Glas­ 3 A European fusion programme to be proud of ses, immersive headsets and motion trackers allow her to 4 The most successful performance in years study the interior of a tokamak. Picture: CEA 6 An unreal reality pushes fusion science 10 IAEA awards EUROfusion’s work 12 Impressions Research Units 14 COMPASS has changed its point of view 18 How to tame plasma turbulence 18 21 Mix it up! The simulation of electrostatic potential along 22 News the torus lines inside a fusion experiment. These experiments help to find origins of plasma turbulence.. Community Picture: GYRO/General Atomics 24 Supernovae in the lab – powered by EUROfusion 28 Pushing the science beyond fusion 30 Young faces of fusion – Robert Abernethy 12 Fuel for Thought Who says operators at the Czech tokamak 33 Combining Physics and Management Forces COMPASS don’t have a sense Perspectives of humour? – More amusing details from fusion on page 12 and 13. 34 Summing Up Picture: EUROfusion EUROfusion © Tony Donné (EUROfusion Programme Manager) Imprint Programme Management Unit – Garching 2016. FUSION IN EUROPE Boltzmannstr. 2 This newsletter or parts of it may not be reproduced ISSN 1818­5355 85748 Garching / Munich, Germany without permission. Text, pictures and layout, except phone: +49-89-3299-4128 where noted, courtesy of the EUROfusion members.
    [Show full text]
  • MHD Stability and Disruptions in the SPARC Tokamak
    MHD stability and disruptions in the SPARC tokamak Downloaded from: https://research.chalmers.se, 2021-09-27 10:20 UTC Citation for the original published paper (version of record): Sweeney, R., Creely, A., Doody, J. et al (2020) MHD stability and disruptions in the SPARC tokamak Journal of Plasma Physics, 86(5) http://dx.doi.org/10.1017/S0022377820001129 N.B. When citing this work, cite the original published paper. research.chalmers.se offers the possibility of retrieving research publications produced at Chalmers University of Technology. It covers all kind of research output: articles, dissertations, conference papers, reports etc. since 2004. research.chalmers.se is administrated and maintained by Chalmers Library (article starts on next page) J. Plasma Phys. (2020), vol. 86, 865860507 © The Author(s), 2020. 1 Published by Cambridge University Press This is an Open Access article, distributed under the terms of the Creative Commons Attribution-NonCommercial-NoDerivatives licence (http://creativecommons.org/licenses/by-nc-nd/4.0/), which permits non-commercial re-use, distribution, and reproduction in any medium, provided the original work is unaltered and is properly cited. The written permission of Cambridge University Press must be obtained for commercial re-use or in order to create a derivative work. doi:10.1017/S0022377820001129 MHD stability and disruptions in the SPARC tokamak R. Sweeney 1,†,A.J.Creely 2,J.Doody1,T.Fülöp 3,D.T.Garnier 1, R. Granetz 1, M. Greenwald 1,L.Hesslow 3,J.Irby1,V.A.Izzo 4, R. J. La Haye5,N.C.Logan 6,K.Montes 1,C.Paz-Soldan 5,C.Rea 1, R.
    [Show full text]
  • European Consortium for the Development of Fusion Energy European Consortium for the Development of Fusion Energy CONTENTS CONTENTS
    EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy EuropEan Consortium for thE DEvElopmEnt of fusion EnErgy Contents Contents introDuCtion ReseaRCH units CooRDinating national ReseaRCH FoR euRofusion 16 agenzia nazionale per le nuove tecnologie, l’energia e lo sviluppo economico sostenibile (enea), italy euRofusion: eMboDying tHe sPiRit oF euRoPean CollaboRation 17 FinnFusion, finland 4 the essence of fusion 18 fusion@Öaw, austria the tantalising challenge of realising fusion power 19 hellenic fusion research unit (Hellenic Ru), greece the history of European fusion collaboration 20 institute for plasmas and nuclear fusion (iPFn), portugal 5 Eurofusion is born 21 institute of solid state physics (issP), latvia the road from itEr to DEmo 22 Karlsruhe institute of technology (Kit), germany 6 Eurofusion facts at a glance 23 lithuanian Energy institute (lei), lithuania 7 itEr facts at a glance 24 plasma physics and fusion Energy, Department of physics, technical university of Denmark (Dtu), Denmark JEt facts at a glance 25 plasma physics Department, wigner Fusion, hungary 8 infographic: Eurofusion devices and research units 26 plasma physics laboratory, Ecole royale militaire (lPP-eRM/KMs), Belgium 27 ruder Boškovi´c institute, Croatian fusion research unit (CRu), Croatia 28 slovenian fusion association (sFa), slovenia 29 spanish national fusion laboratory (lnF), CiEmat, spain 30 swedish research Council (vR), sweden rEsEarCh unit profilEs 31 sylwester Kaliski institute of plasma physics and laser microfusion (iPPlM), poland 32 the institute
    [Show full text]
  • The High-Field Path to Practical Fusion Energy
    The High-Field Path to Practical Fusion Energy M. Greenwald, D. Whyte, P. Bonoli, Z. Hartwig, J. Irby, B. LaBombard, E. Marmar, J. Minervini, M. Takayasu, J. Terry, R. Vieira, A. White, S. Wukitch MIT – Plasma Science & Fusion Center D. Brunner, R. Mumgaard, B. Sorbom Commonwealth Fusion Systems This white paper outlines a vision and describes a coherent roadmap to achieve practical fusion energy in less time and at less expense than the current pathway. The key technologies that enable this path are high-field, high-temperature superconducting magnets, a molten salt liquid blanket, high-field-side lower hybrid current drive and a long-legged, advanced divertor. We argue that successful development and integration of these innovative and synergistic technologies would dramatically change the outlook for fusion, providing a real opportunity to positively impact global climate change and to reverse the loss of U.S. leadership in fusion research suffered in recent decades. An illustration of the SPARC tokamak – a compact, net-energy tokamak that would be a key step on the high field path to fusion. Credit: Ken Filar https://commons.wikimedia.org/wiki/File%3ASparc_february_2018.jpg The High-Field Path to Practical Fusion Energy Table of Contents 1. Executive summary .............................................................................................................. 2 2. High Temperature Superconductors ................................................................................... 5 3. SPARC – A Compact, Net-Energy Fusion Experiment
    [Show full text]
  • Fusion in Europe News & Views on the Progress of Fusion Research
    FUSION IN EUROPE NEWS & VIEWS ON THE PROGRESS OF FUSION RESEARCH WHY FUSION? SUMMER 2019 FUSION IN EUROPE SUMMER 2019 Contents LOOKING INTO THE WHY FUSION? 6 CRYSTAL BALL 8 We asked and the fusion community answered! Marie-Line Mayoral explains how modelling is taking fusion Picture: Sarah McKellar on Unsplash experiments to the next level. Picture: Holger Link on Unsplash PSI-2 LINEAR PLASMA OUTSIDE INSIGHTS: DEVICE POSTER ALTERNATIVE FUSION 12 14 See where materials are put through the ultimate Science writer Daniel Clery looks at the race to realise plasma test. Picture: Christophe Roux, CEA, France fusion. Picture: General Fusion Imprint © Petra Nieckchen, Head of Communications Dept. FUSION IN EUROPE This magazine or parts of it may not be reproduced ISSN 1818-5355 without permission. Text, pictures and layout, except where noted, courtesy of the EUROfusion members. EUROfusion The EUROfusion members are the Research Units Programme Management Unit – Garching of the European Fusion Programme. Responsibility Boltzmannstr. 2 for the information and views expressed in this 85748 Garching / Munich, Germany newsletter lies entirely with the authors. Neither phone: +49-89-3299-4128 the Research Units or anyone acting on their behalf For more information see the email: [email protected] is responsible for any damage resulting from the website: www.euro-fusion.org editor: Karl Tischler use of information contained in this publication. 2 FUSION IN EUROPE | Summer 2019 | EUROfusion | LETTER FROM THE EDITOR Dear Reader, As we bake under record-breaking heat waves again this year, it is harder to ignore that climate change means that we have to make changes.
    [Show full text]
  • 3Rd IAEA Technical Meeting on Divertor Concepts
    WORKING MATERIAL ABSTRACTS AND MEETING MATERIAL 3rd IAEA Technical Meeting on Divertor Concepts IAEA Headquarters, Vienna, Austria, 4–7 November 2019 indico/event/192 DISCLAIMER This is not an official IAEA publication. The views expressed herein do not necessarily reflect thoseof the IAEA or its Member States. This document should not be quoted or cited as an official publication. The use of particular designations of countries or territories does not imply any judgement by the IAEA, as to the legal status of such countries or territories, of their authorities and institutions or of the delimitation of their boundaries. The mention of names of specific companies or products (whether or not indicated as registered) does not imply any intention to infringe proprietary rights, nor should it be construed as an endorsement or recommendation on the part of the IAEA. 1 Preface Nuclear fusion is recognised as a long-term energy source. The International Atomic Energy Agency (IAEA) fosters the exchange of scientific and technical results in nuclear fusion research and devel- opment through its series of Technical Meetings and workshops. The Third Technical Meeting on Divertor Concepts (DC 2019) aimed to provide a forum for dis- cussing and analyzing the latest findings and open issues related to the divertor of a fusion device in the context of DEMO. The event focused on an integral approach, i.e. connecting plasma physics and engineering aspects, and aimed at an intensive exchange of ideas on the different aspects that the divertor design and fusion machine operation involve, from ITER divertor developments to innovative technologies for DEMO divertor.
    [Show full text]