Overview of first Wendelstein 7-X high-performance operation
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Tutkijat
Organisaatiot
- University of Greifswald
- Max Planck Inst Plasma Phys, Max Planck Society
- Tech Univ Denmark, Technical University of Denmark, Dept Phys, Assoc EURATOM DTU
- Princeton Plasma Phys Lab, Princeton Physics Laboratory, Princeton University, United States Department of Energy (DOE)
- Natl Inst Fus Sci, National Institute for Fusion Science (NIFS) - Japan, National Institutes of Natural Sciences (NINS) - Japan
- CIEMAT
- Assoc EURATOM HAS, Euratom, Hungarian Academy of Sciences, Wigner Res Ctr Phys
- MIT, Massachusetts Institute of Technology (MIT), Ctr Space Res
- University of Wisconsin-Madison
- Res Ctr Julich GmbH, Research Center Julich, Helmholtz Association, Inst Energy & Climate Res Plasma Phys
- Australian National University
- Eindhoven University of Technology
- University of Cagliari
- Consorzio RFX
- Univ Lisbon, Universidade de Lisboa, Inst Super Tecn, Inst Plasmas & Fusao Nucl
- CEA Cadarache
- Russian Acad Sci, Ioffe Physical Technical Institute, Russian Academy of Sciences, St. Petersburg Scientific Centre of the Russian Academy of Sciences, Ioffe Phys Tech Inst
- Oak Ridge Natl Lab, Oak Ridge National Laboratory, United States Department of Energy (DOE)
- University of Salerno
- ENEA Ctr Ric Frascati, Italian National Agency New Technical Energy & Sustainable Economics Development
- Inst Plasma Phys & Laser Microfus, Institute of Plasma Physics & Laser Microfusion (IFPiLM)
- University of Szczecin
- Univ Milano Bicoccae, Euratom, University of Milano-Bicocca, EURATOM ENEA CNR Assoc Fus
- Royal Mil Acad
- Auburn University
- Karlsruhe Institute of Technology
- Univ Carlos III Madrid, Universidad Carlos III de Madrid, Dept Fis
- Univ Stuttgart, University of Stuttgart, Inst Surface Proc Engn & Plasma Technol
- Austrian Acad Sci, Austrian Academy of Sciences
- Inst Nucl Res, National Academy of Sciences Ukraine, Institute for Nuclear Research of NASU, V. M. Glushkov Institute of Cybernetics, National Academy of Sciences of Ukraine
- Technical University of Berlin
- Opole Univ Technol, Opole University of Technology
- Univ Maryland, University System of Maryland, University of Maryland College Park, Dept Phys
- CNR, Istituto Fisica del Plasma "Piero Caldirola" (IFP-CNR), Consiglio Nazionale delle Ricerche (CNR), Ist Fis Plasma
- Kyoto Univ, Kyoto University, Grad Sch Informat, Dept Appl Math & Phys, Sakyo Ku
- Culham Ctr Fus Energy
- Physikalisch-Technische Bundesanstalt (PTB)
- Los Alamos Natl Lab, Los Alamos National Laboratory, United States Department of Energy (DOE)
- Max Planck Institute for Plasma Physics
Kuvaus
The optimized superconducting stellarator device Wendelstein 7-X (with major radius R = 5.5 m, minor radius a = 0.5 m, and 30 m(3) plasma volume) restarted operation after the assembly of a graphite heat shield and 10 inertially cooled island divertor modules. This paper reports on the results from the first high-performance plasma operation. Glow discharge conditioning and ECRH conditioning discharges in helium turned out to be important for density and edge radiation control. Plasma densities of 1-4.5 x 10(19) m(-3) with central electron temperatures 5-10 keV were routinely achieved with hydrogen gas fueling, frequently terminated by a radiative collapse. In a first stage, plasma densities up to 1.4 x 10(20) m(-3) were reached with hydrogen pellet injection and helium gas fueling. Here, the ions are indirectly heated, and at a central density of 8 . 10(19 )m(-3) a temperature of 3.4 keV with T-e/T-i = 1 was transiently accomplished, which corresponds to nT(i)(0)tau(E) = 6.4 x 10(19) keV s m(-3) with a peak diamagnetic energy of 1.1 MJ and volume-averaged normalized plasma pressure = 1.2%. The routine access to high plasma densities was opened with boronization of the first wall. After boronization, the oxygen impurity content was reduced by a factor of 10, the carbon impurity content by a factor of 5. The reduced (edge) plasma radiation level gives routinely access to higher densities without radiation collapse, e.g. well above 1 x 10(20) m(-2) line integrated density and T-e = T-i = 2 keV central temperatures at moderate ECRH power. Both X2 and O2 mode ECRH schemes were successfully applied. Core turbulence was measured with a phase contrast imaging diagnostic and suppression of turbulence during pellet injection was observed.
Yksityiskohdat
Alkuperäiskieli | Englanti |
---|---|
Artikkeli | 112004 |
Sivut | 1-11 |
Sivumäärä | 11 |
Julkaisu | Nuclear Fusion |
Vuosikerta | 59 |
Numero | 11 |
Tila | Julkaistu - marraskuuta 2019 |
OKM-julkaisutyyppi | A1 Julkaistu artikkeli, soviteltu |
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ID: 34924520