The Legacy of Masahiro Wakatani

Total Page:16

File Type:pdf, Size:1020Kb

The Legacy of Masahiro Wakatani J. Plasma FusionFusion Res.Res. SERIES,SERIES, Vol. Vol. 6 6(2004) (2004) 100–106 000–000 The Legacy of Masahiro Wakatani VAN DAM James W. and HORTON C. Wendell, Jr. Institute for Fusion Studies, The University of Texas, Austin, Texas 78712, USA (Received: 18 February 2004 / Accepted: 7 April 2004) Abstract As a memorial to Masahiro Wakatani, late professor of plasma physics at Kyoto University, a review is given of his legacy of achievements in scientific research, international collaborations, university administration, student guidance, and personal life. Keywords: Hasegawa-Wakatani equation, turbulent transport, helical system stability, drift wave, reduced MHD equation 1. Introduction Division (1976-1978). The international community of fusion plasma physicists In 1978 he joined the Plasma Physics Laboratory at was deeply saddened by the unexpected loss of one of its Kyoto University as an Associate Professor. He was promoted most respected members, Prof. Masahiro Wakatani, of Kyoto to full Professor in 1985. In 1996 he became a Professor in University, who died from a cerebral hemorrhage on 9 the Department of Fundamental Energy Science and the January 2003. This paper, based on a talk [1] presented during Department of Nuclear Engineering. a special memorial session at the 13th International Toki He was elected a Fellow of the American Physical Conference (9-12 December 2003), is offered as a tribute in Society in 1990. his memory. He died on 9 January 2003. Two obituaries about him Professor Wakatani had a brilliant career as a scientific have been published [2,3]. researcher, international collaborator, university leader, and teacher. In this paper, after providing a brief biographical 3. Legacy of innovative research sketch, we will describe each of these aspects of his very Without question Wakatani was one of the very best significant legacy and also offer some personal comments theoretical and computational plasma physicists in the world. about him. He published many influential papers. His creative and original work on nonlinear MHD, drift wave instabilities, 2. Capsule biography stellarator confinement, and ion-temperature-gradient mode Here we briefly list some selected biographical details dynamics is famous. Here we provide a brief description of and important dates in his career. This list will serve as a his major contributions to several areas of theoretical plasma chronological framework for the description of his many physics research. accomplishments. According to Prof. Tokuhiro Obiki’s obituary [2], He was born on 15 May 1945, in Osaka, Japan. Wakatani’s scientific talent and brilliance were already He attended Kyoto University for his undergraduate and obvious in his student days. He had the highest marks of any graduate education. He graduated with a B.Sc. degree (1968) student ever in nuclear engineering. For his Ph.D. thesis, he and a Master’s degree (1970) in nuclear engineering. He then carried out the first application of neoclassical theory to the obtained a Dr.Eng. degree in electrical engineering (1973) toroidal pinch confinement device. He used the neoclassical with a thesis entitled “Magnetohydrodynamic Equilibrium and theory of Roald Sagdeev and Alec Galeev, which was brand Stability of Toroidal Pinches” under the guidance of his thesis new at that time, to calculate the collisional diffusion advisor, Prof. Ryohei Itatani. coefficients in a toroidal pinch [4]. After graduation, he was first employed at the Japan After graduation, he continued his work on stability and Atomic Energy Research Institute as a Research Associate in transport, switching his attention first to the tokamak device, the Division of Thermonuclear Research (1973-1976). which had much better confinement than the toroidal pinch, Subsequently he went to the Institute of Plasma Physics, and (when he joined the faculty at Kyoto University) also to Nagoya University, as a Research Associate in the Theory ©2004 by The Japan Society of Plasma Corresponding author’s e-mail: [email protected] Science and Nuclear Fusion Research 1001 Van Dam J.W. et al., The Legacy of Masahiro Wakatani helical confinement devices, especially the Heliotron/torsatron used in some recent experimental work [10] to explain shear line. A major scientific accomplishment, published in the year flow-induced transport barriers. that he moved back to Kyoto, was his derivation of reduced Wakatani was clearly a world leader in the studies of MHD equations for helical systems [5]. These equations were drift wave and resistive-g mode turbulence. He was unique in derived by means of an averaging approach, based on the that he not only developed a simple paradigm model (namely, “stellarator expansion technique.” They are a simplified the two-dimensional Hasegawa-Wakatani equations with one version of the full MHD equations, but yet retain the essential parameter), but also constructed technically complete models helical physics and – quite importantly – are amenable to for three-dimensional helical systems. He gained an nonlinear numerical simulations. These reduced equations are international reputation for his work on drift wave instabilities still today the popular standard model, used worldwide for in toroidally confined plasmas. His studies of anomalous MHD analysis and machine design. transport induced by ion temperature gradient (ITG) and Perusal of his extensive list of publications leads to an electron temperature gradient (ETG) instabilities are well appreciation of how much work he did on analyzing Heliotron known. One of us had the privilege of co-authoring a series experimental results. He was a co-author on many papers of ITG and ETG papers with Wakatani and also several of dealing with pellet injection, heating, equilibrium, stability, his students (especially Dr. Hideo Sugama) [11]. transport and confinement, etc., in Heliotron experiments [6]. Wakatani and his students skillfully used large-scale Furthermore, he, with his students, carried out studies of a computing for attacking complex systems. A rather recent Helias-Heliac hybrid stellarator [7] and helped with the design example was his work on simulating the dangerous plasma of the Heliotron-J device, which was subsequently constructed transport due to electron-temperature-gradient turbulence in and is now operating at Kyoto University. Heliotron-J is a reversed-shear, nearly collisionless toroidal systems with a helical axis device, based on the quasi-isodynamic (i.e., quasi- record number of representative electrons per cell in a self- omnigenous) optimization approach to the helical-axis consistent field [12]. Heliotron line. In addition to doing original research, he somehow found In the early 1980’s, shortly after the launch of the U.S.- time to publish five books. He co-authored two textbooks with Japan fusion theory exchange activities (to be described in Prof. Kyoji Nishikawa. The first, Physics of Continuous Sec. 4), Wakatani began to study anomalous transport due to Fluids [13], unfortunately available only in Japanese, covers turbulence arising from micro-instabilities, a major obstacle material from low-temperature quantum fluids to high- to improved plasma confinement. In 1983, working with Dr. temperature plasmas. Their other jointly written book, Plasma Akira Hasegawa (then at Bell Lab), he derived a set of Physics: Basic Theory with Fusion Applications [14], was nonlinear evolution equations that describe strong turbulence used by us as a graduate-level text at the University of Texas caused by resistive drift-wave instability at the edge of a and has been reprinted in three editions so far. Two of plasma [8]. Using these equations, they showed the existence Wakatani’s other books were related to U.S.-Japan exchange of an inverse cascade of energy from short to long activities. One was a conference proceedings, U.S.-Japan wavelengths in plasma turbulence. They also found a Workshop on Ion Temperature Gradient-Driven Turbulent prototype mechanism for generating large-scale poloidal flow Transport, Austin, TX, 1993 [15]. Another arose out a series structures (e.g., zonal flows and streamers in tokamaks). of U.S.-Japan workshops, which he helped to organize, and These “Hasegawa-Wakatani equations” for nonlinear scientific exchange visits, in which he participated (mostly drift waves have become extremely well known and hence with scientists at New York University), concerning the deserve special notice in any description of Wakatani’s development of the BETA equilibrium, stability, and transport accomplishments. We speculate that perhaps because he lived codes and their application for stellarator design [16]. in the ancient cultural region of Kyoto and Nara, he liked Unquestionably his magnum opus was his final book, theories that were simple, orderly, and yet elegant, like a Zen Stellarator and Heliotron Devices [17]. This text is extremely garden. Thus, the Hasegawa-Wakatani theory created a highly well written, providing both physical pictures as well as simplified formulation of the drift wave equations, in which detailed descriptions, and covering not only MHD and two coupled nonlinear partial differential equations provide a resistive MHD physics but also drift wave physics (very powerful paradigm for studying the transition from collisional important for helical plasmas) – in short, a veritable “bible” drift wave turbulence to collisionless drift waves, all in terms of stellarator theory. of a single parameter. These equations immediately became An impressive
Recommended publications
  • Identification of Coherent Magneto-Hydrodynamic Modes and Transport in Plasmas of the Tj-Ii Heliac
    TESIS DOCTORAL IDENTIFICATION OF COHERENT MAGNETO-HYDRODYNAMIC MODES AND TRANSPORT IN PLASMAS OF THE TJ-II HELIAC Autor: Baojun Sun Directores: Daniel López Bruna María Antonia Ochando García Tutor: Víctor Tribaldos Macía DEPARTAMENTO DE FISICA Leganés, septiembre de 2016 ( a entregar en la Oficina de Posgrado, una vez nombrado el Tribunal evaluador , para preparar el documento para la defensa de la tesis) TESIS DOCTORAL IDENTIFICATION OF COHERENT MAGNETO-HYDRODYNAMIC MODES AND TRANSPORT IN PLASMAS OF THE TJ-II HELIAC Autor: Baojun Sun Directores: Daniel López Bruna Maria Antonia Ochando Garcia Firma del Tribunal Calificador: Firma Presidente: (Nombre y apellidos) Vocal: (Nombre y apellidos) Secretario: (Nombre y apellidos) Calificación: Leganés/Getafe, de de Acknowledgements Once I recalled, the motivation that drove me to change major to fusion was twofold: 1. I saw fusion as the ultimate resource of energy and I expected to witness the construction of ITER; 2. I had the curiosity, the beliefs and the expectation. Chinese philosopher Chuang Tzu, said “newborn calves are not afraid of tigers”, this quote may describe my 5 year adventure. “Being as a newborn calf” makes me to be in trouble but also helps me to get out. What is PhD? In the beginning, I didn’t make myself this question seriously. As a newborn calf, I believed PhD as a chance and thought my PhD would innovate the research field. After about two years of turmoil, the question came again, what is PhD? Istartedto think PhD was about solving a unanswered question. My story was nearly ended there at that moment, but I was a lucky man, since I met with Daniel López Bruna (Daniel) and María Antonia Ochando García (Marian), and later on they became my Thesis directors.
    [Show full text]
  • Stellarator News Issue 67
    Published by Fusion Energy Division, Oak Ridge National Laboratory Building 9201-2 P.O. Box 2009 Oak Ridge, TN 37831-8071, USA Editor: James A. Rome Issue 67 January 2000 E-Mail: [email protected] Phone (865) 574-1306 Fax: (865) 574-7624 On the Web at http://www.ornl.gov/fed/stelnews 1–1.5 T, the vacuum rotational transform is 0.3–0.8 with First plasmas in Heliotron J low magnetic shear, and the magnetic well depth is 1.5% at the plasma edge. Heating systems include 0.5-MW The Heliotron J Group is very happy to announce that at ECH, 1.5-MW neutral beam injection (NBI), and 2.5-MW 7:06 PM on Thursday, 2 December 1999, Heliotron J ion cyclotron resonant frequency heating (ICRH). achieved its first hydrogen discharge by using 1 kW of T. Obiki, F. Sano, K. Kondo,* M. Wakatani,* T. Mizuuchi, 2.45-GHz electron cyclotron heating (ECH) at a magnetic K. Hanatani, Y. Nakamura,* K. Nagasaki, H. Okada, M. Naka- field of 500 G, for discharge cleaning. At 3:57 PM on suga,* S. Besshou,* and M. Yokoyama** Wednesday, 8 December, Heliotron J achieved its first E-mail: [email protected] 53.2-GHz ECH plasma with 300 kW of heating power at a field of 1 T, with an ECH pulse length of about 10 ms. The Institute of Advanced Energy, Kyoto University, Japan *Graduate School of Energy Science, Kyoto University, Japan pulse length is now being increased shot by shot. Figure 1 **National Institute for Fusion Science, Toki, Japan shows the 53.2-GHz ECH plasma as viewed through one of the tangential ports.
    [Show full text]
  • 1 Input from the US Stellarator Research Community to the FESAC
    Input from the US Stellarator Research Community to the FESAC Panel on Toroidal Alternates June 2008 Abstract International research carried out over the past 5 decades has steadily validated the ability of the stellarator magnetic configuration to confine high performance, macroscopically quiescent plasmas with inherent steady-state capability. Sharing many of the same physics characteristics as tokamaks, stellarators attain similar plasma parameters and figures of merit to comparably-sized tokamaks. In conjunction with ongoing tokamak research in the burning plasma era, work on stellarators over the next twenty years is intended to develop the stellarator concept to be ready to proceed to a DEMO-scale experiment. Apart from the plasma-wall interaction and materials problems that confront all steady-state toroidal reactor concepts, the stellarator does not exhibit a clear scientific ‘show-stopper’ that would preclude it from successfully confining a burning DT plasma. The main challenges confronting the stellarator concept specifically are to validate that our understanding of 3D plasma confinement physics extends to fusion relevant plasma parameters and to systematically develop system designs that accommodate the complexity of the highly-shaped, three-dimensional plasma configuration and the magnet coils that produce it. The progress of the stellarator toward its DEMO goal will be facilitated to a great extent if the stellarator coils can be simplified while still producing the magnetic configuration required for good confinement, stability, and fusion gain. To do so will require improved understanding of the behavior of existing and future stellarator plasmas coupled with the ability to provide the necessary shaping of the 3-D magnetic flux surfaces with an efficiently-engineered set of coils.
    [Show full text]
  • Effect of ECH/ECCD on Energetic-Particle-Driven MHD Modes in Helical Plasmas
    PAPER • OPEN ACCESS Effect of ECH/ECCD on energetic-particle-driven MHD modes in helical plasmas To cite this article: S. Yamamoto et al 2020 Nucl. Fusion 60 066018 View the article online for updates and enhancements. This content was downloaded from IP address 130.54.110.24 on 02/06/2020 at 13:08 International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 60 (2020) 066018 (12pp) https://doi.org/10.1088/1741-4326/ab7f13 Effect of ECH/ECCD on energetic-particle-driven MHD modes in helical plasmas S. Yamamoto1, K. Nagasaki2, K. Nagaoka3,4, J. Varela3, A.´ Cappa5, E. Ascasíbar5, F. Castejon´ 5, J.M. Fontdecaba5, J.M. García-Regaña5, A.´ Gonz´alez-Jerez5, K. Ida3,6, A. Ishizawa 7, M. Isobe3,6, S. Kado2, S. Kobayashi2, M. Liniers5, D. Lopez-Bruna´ 5, N. Marushchenko 8, F. Medina5, A. Melnikov9,10, T. Minami2, T. Mizuuchi2, Y. Nakamura7, M. Ochando 5, K. Ogawa3,6, S. Ohshima2, H. Okada2, M. Osakabe3,6, M. Sanders11, J.L. Velasco 5, G. M. Weir8 and M. Yoshinuma3,6 1 National Institutes for Quantum and Radiological Science and Technology, Naka, Japan 2 Institute of Advanced Energy, Kyoto University, Uji, Japan 3 National Institute for Fusion Science, Toki, Japan 4 Graduate School of Science, Nagoya University, Nagoya, Japan 5 National Laboratory for Magnetic Fusion, CIEMAT, Madrid, Spain 6 The Graduate University for Advanced Studies, SOKENDAI, Toki, Japan 7 Graduate School of Energy Science, Kyoto University, Uji, Japan 8 Max-Planck-Institute for Plasma Physics, Greifswald, Germany 9 National Research Centre ‘Kurchatov Institute’, Moscow,
    [Show full text]
  • History of Nuclear Fusion Research in Japan
    H-PTh-14 History of Nuclear Fusion Research in Japan Harukazu IGUCHI, Keisuke MATSUOKA1, Kazue KIMURA, Chusei NAMBA, and Shinzaburo MATSUDA2 Fusion Science Archives, National Institute for Fusion Science, Toki 509-5292, Japan 1 Prof. Emeritus of National Institute for Fusion Science, Japan. 2 Tokyo Institute of Technology, Tokyo 152-8550, Japan E-mail:[email protected] The atomic energy research was declassified worldwide at the International Conference on the Peaceful Uses of Atomic Energy in 1955. In the late 1950s there was a lively discussion among scientists on the strategy of nuclear fusion research in Japan, leading to the conclusion that fusion research should be started from the basic, namely, research on plasma physics and from cultivation of human resources at universities under the Ministry of Education, Science and Culture (MOE). However, an endorsement was given that construction of an experimental device for fusion research would be approved sooner or later. Meanwhile, confinement studies were conducted specifically in USSR and USA with tokamaks and multipoles, respectively. In Japan, studies on toroidal plasma confinement started at Japan Atomic Energy Research Institute (JAERI) under the Science and Technology Agency (STA) in the mid-1960s. Successful results from tokamak researches in USSR encouraged scientists worldwide, which resulted in construction rush of tokamaks in Japan, too. However, dualistic fusion research framework established in 1960s has lasted until now; MOE for science and STA for development. World Trend in Early Days as a Background Extracted from “Presidential Address at the 1st International REVIEW OF EXPERIMENTAL The 3rd IAEA Conf. on Nuclear Fusion at Novosibirsk, 1968 Conference on the Peaceful Uses of Atomic Energy” by Mr.
    [Show full text]
  • Fusion Energy Conference 2006 Book of Abstracts
    Fusion Energy Conference 2006 Book of Abstracts Contents Overview (OV) 1 OV/1-1 · Overview progress and future plan of EAST Project . 2 OV/1-2 · Overview of JT-60U Results for Development of Steady-State Advanced Toka- mak Scenario . 2 OV/1-3 · Overview of JET Results . 2 OV/1-4 · Development in the DIII-D Tokamak of Advanced Operating Scenarios and Associated Control Techniques for ITER . 3 OV/2-1 · Extended Steady-State and High-Beta Regimes of Net-Current Free Heliotron Plasmas in the Large Helical Device . 3 OV/2-2 · Overview of ASDEX Upgrade Results . 4 OV/2-3 · Overview of Physics Results from MAST . 4 OV/2-4 · Recent Physics Results from the National Spherical Torus Experiment . 5 OV/3-1 · Integration of High Power, Long Pulse Operation in Tore Supra in Preparation for ITER . 5 OV/3-2 · Overview of Alcator C-Mod Research Program . 6 OV/3-3 · Overview of TCV Results . 6 OV/3-4 · Overview of the FTU results . 7 OV/4-1 · Overview of HL-2A Experiment Results . 7 OV/4-2 · Overview of TJ-II experiments . 8 OV/4-3 · Overview of T-10 Results . 8 OV/4-4 · Experimental Progress on Zonal Flow Physics in Toroidal Plasmas . 8 OV/5-1 · Recent Progress on FIREX Project and Related Fusion Researches at ILE, Osaka 9 OV/5-2 · Overview of Inertial Fusion Research in the United States . 9 OV/5-3 · Theory of Alfv´enwaves and energetic particle physics in burning plasmas . 9 OV/5-4 · Status of R&D Activities on Materials for Fusion Power Reactors .
    [Show full text]
  • 16Th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems — Theory of Plasma Instabilities
    WORKING MATERIAL ABSTRACTS AND MEETING MATERIAL 16th IAEA Technical Meeting on Energetic Particles in Magnetic Confinement Systems — Theory of Plasma Instabilities Shizuoka, Japan, 3–6 September 2019 indico/event/185 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 16th Technical Meeting on Energetic Particles in Magnetic Confinement Systems — Theory of Plasma Instabilities (EPPI 2019) was the first joint meeting of experts from the two scientific disciplines. The event aimed to provide a forum to discuss the status of experimental and theoretical work on suprathermal electrons and ions in a wide variety of magnetic confinement geometries, and to discuss theoretical and computational physics issues relevant to burning plasmas. The EPPI 2019 was organized by the IAEA, in cooperation with the Government of Japan through the National Institute for Fusion Science, in Shizuoka City, Japan.
    [Show full text]
  • Conference Series 591 (2015) 012016 Doi:10.1088/1742-6596/591/1/012016
    View metadata, citation and similar papers at core.ac.uk brought to you by CORE provided by Repositorio Institucional del Instituto Tecnologico de Costa Rica Home Search Collections Journals About Contact us My IOPscience Constructing a small modular stellarator in Latin America This content has been downloaded from IOPscience. Please scroll down to see the full text. 2015 J. Phys.: Conf. Ser. 591 012016 (http://iopscience.iop.org/1742-6596/591/1/012016) View the table of contents for this issue, or go to the journal homepage for more Download details: IP Address: 201.206.114.2 This content was downloaded on 23/03/2017 at 21:01 Please note that terms and conditions apply. You may also be interested in: SCR-1: Design and Construction of a Small Modular Stellarator for Magnetic Confinement of Plasma L Barillas, V I Vargas, A Alpizar et al. Major issues in the design and construction of the stellarator of Costa Rica: SCR-1 J Mora, V I Vargas, L F Villegas et al. 15th Latin American Workshop on Plasma Physics (LAWPP2014) IOP Publishing Journal of Physics: Conference Series 591 (2015) 012016 doi:10.1088/1742-6596/591/1/012016 Constructing a small modular stellarator in Latin America V.I. Vargas, J. Mora, J. Asenjo, E. Zamora, C. Otárola, L. Barillas, J. Carvajal- Godínez, J. González-Gómez, C. Soto-Soto and C. Piedras Plasma Laboratory for Fusion Energy and Applications, Cartago, Costa Rica Instituto Tecnológico de Costa Rica, Cartago, Costa Rica E-mail: [email protected]. Abstract. This paper aims at briefly describing the design and construction issues of the stellarator of Costa Rica 1 (SCR-1).
    [Show full text]
  • Opportunities in the Fusion Energy Sciences Program Appendix C
    Cover design adapted with permission of the Contemporary Physics Education Project from the wall chart “Fusion—Physics of a Fundamental Energy Source” (http://FusEdWeb.pppl.gov/CPEP/chart.html). OPPORTUNITIES IN THE FUSION ENERGY SCIENCES PROGRAM Appendix C TOPICAL AREAS CHARACTERIZATION June 1999 Prepared by the Fusion Energy Sciences Advisory Committee for the Office of Science of the U.S. Department of Energy On the World Wide Web: http://wwwofe.er.doe.gov/More_HTML/FESAC_Charges_Reports.html ii PREFACE This document has been prepared in response to a charge to the Fusion Energy Sciences Advisory Com- mittee (FESAC) from Dr. Martha Krebs, Director of the Department of Energy’s Office of Science: ... to make final a program plan for the fusion energy science program by the end of 1999 (FY). Such a program plan needs to include paths for both energy and science goals taking into account the expected overlap between them. The plan must also address the needs for both magnetic and inertial confinement options. It will have to be specific as to how the U.S. program will address the various overlaps, as well as international collaboration and funding constraints. Finally, this program plan must be based on a ‘working’ consensus (not unanim- ity) of the community, otherwise we can’t move forward. Thus I am turning once again to FESAC. I would like to ask FESAC’s help in two stages. First, please prepare a report on the opportunities and the requirements of a fusion energy science program, including the tech- nical requirements of fusion energy. In preparing the report, please consider three time-scales: near-term, e.g., 5 years; mid-term, e.g., 20 years; and the longer term.
    [Show full text]
  • Stellarator Agreement
    Implementing Agreement for Cooperation in Development of the Stellarator Concept 2009 Executive Committee Annual Report to the Fusion Power Coordination Committee January 2010 Committee Chair: O. Motojima (National Institute for Fusion Science, Japan) Committee Members: D.T. Anderson (Wisconsin University, USA) B. Blackwell (The Australian National University, Australia) J. H. Harris (The Australian National University, Australia) A. Komori (National Institute for Fusion Science, Japan) L. M. Kovrizhnikh (Institute of General Physics, Russian Academy of Science, Russia) O. Motojima (National Institute for Fusion Science, Japan) D. Prokhorv (ROSATOM, Russia) J. Sanchez (Laboratorio Nacional de Fusión, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Spain) V. I. Tereshin (Institute of Plasma Physics of the National Scientific Center, Kharkov Institute of Physics and Technology, Ukraine) E. D. Volkov (Institute of Plasma Physics of the National Scientific Center, Kharkov Institute of Physics and Technology, Ukraine) R. Wolf (Max-Planck-Institut für Plasmaphysik, Germany) M. C. Zarnstorff (Princeton Plasma Physics Laboratory, USA) Alternates: T. Klinger (Max-Planck-Institut für Plasmaphysik, Germany) C. Hidalgo (Laboratorio Nacional de Fusión, Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas, Spain) Secretary: H. Yamada (National Institute for Fusion Science, Japan) 1/85 EXECUTIVE SUMMARY The present report overviews the scientific and technical progress achieved in 2009 by the parties to the Stellarator
    [Show full text]
  • Stellarator News Issue
    An international journal of news from the stellarator community Editor: James A. Rome Issue 161 April 2018 E-Mail: [email protected] Phone: +1 (865) 482-5643 On the Web at https://stelnews.info The test divertor was installed for the recently conducted Wendelstein 7-X status update campaign and experiments to be carried out in 2018, and is part of a long-term strategy to extend plasma pulse length. First divertor operation: higher plasma densi- Prior to this experimental campaign, ten divertor units had ties, longer discharges been installed. Even without water cooling, the test diver- tor units are more tolerant to unexpected loads and thus an Shortly before Christmas, the 2017 experimental cam- ideal tool for first divertor tests. Consequently, the goals of paign on Wendelstein 7-X (W7-X) was completed as this divertor phase were to gain experience with the mag- planned. Starting in early September, fifteen weeks of netic field in the presence of the divertor and to develop operation were conducted and major machine components safe and reliable operation. This will form the basis for worked without failures, allowing the scientists an effi- experiments that will ultimately extend pulse lengths from cient use of the machine time. The W7-X team currently seconds to several minutes. comprises about 150 scientific staff members based in Greifswald and more than 60 scientists from EUROfusion Figure 2 shows how the plasma acts on the divertor. The laboratories, the United States, Japan, and Australia. figure shows thermography data indicating the location of the heat loads. During the campaign the maximum surface Expectations for the experiments were high: after the first temperature on the divertor approached 900 °C after a few campaign, ending in March 2016, W7-X was equipped seconds of the discharge.
    [Show full text]
  • EXC/2-5Ra H-Mode in Helical Devices
    1 EXC/2-5Ra H-mode in Helical Devices M. Hirsch 1), T. Akiyama 2), T. Estrada 3), T. Mizuuchi 4), K. Toi 2), C. Hidalgo 3) 1) Max-Planck-Institut für Plasmaphysik, EURATOM-Ass., D-17489 Greifswald, Germany 2) National Institute for Fusion Science, Toki 509-5292, Japan 3) Asociación EURATOM/CIEMAT, Av. Complutense 22, 28040, Madrid, Spain 4) Institute of Advanced Energy, Kyoto University, Gokasho, Uji, Japan E-mail contact of main author: [email protected] Abstract. L-H transitions and ELMs are observed in all helical devices if operated at relevant plasma conditions thus emphasizing the generic character of these phenomena in toroidal confinement. Particular for helical devices resembling 3D systems is, first, the strong dependency of the H-mode transition and the ELM phenomenology on the magnetic edge configuration and, second, the existence of a sheared radial electric field already before the transition predefined by the ambipolarity condition of the convective fluxes. These elements may constitute biasing preconditions for the spin-up to a high-rotation state. 1. Introduction L-H transition phenomena - the rapid drop of turbulent transport at the plasma edge followed by the development of steep edge gradients and Edge Localized Modes (ELMs) or ELM-like events - have been observed in all helical devices if operated at the relevant plasma conditions: The low-magnetic shear stellarator Wendelstein 7-AS [1], the heliotrons LHD [2,3,4,5,24] and CHS [6,7] with high shear - negative with respect to the tokamak case - and the helical-axis Heliotron J with negative low shear [8] as well as in the heliac TJ-II with low magnetic shear [9,10,11,12].
    [Show full text]