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@ARTICLE{Dinklage:862061,
      author       = {Dinklage, A. and Beidler, C. D. and Helander, P. and
                      Fuchert, G. and Maaßberg, H. and Rahbarnia, K. and Sunn
                      Pedersen, T. and Turkin, Y. and Wolf, R. C. and Alonso, A.
                      and Andreeva, T. and Blackwell, B. and Bozhenkov, S. and
                      Buttenschön, B. and Czarnecka, A. and Effenberg, F. and
                      Feng, Y. and Geiger, J. and Hirsch, M. and Höfel, U. and
                      Jakubowski, M. and Klinger, T. and Knauer, J. and Kocsis, G.
                      and Krämer-Flecken, A. and Kubkowska, M. and Langenberg, A.
                      and Laqua, H. P. and Marushchenko, N. and Mollén, A. and
                      Neuner, U. and Niemann, H. and Pasch, E. and Pablant, N. and
                      Rudischhauser, L. and Smith, H. M. and Schmitz, O. and
                      Stange, T. and Szepesi, T. and Weir, G. and Windisch, T. and
                      Wurden, G. A. and Zhang, D.},
      title        = {{M}agnetic configuration effects on the {W}endelstein 7-{X}
                      stellarator},
      journal      = {Nature physics},
      volume       = {14},
      number       = {8},
      issn         = {1745-2481},
      address      = {Basingstoke},
      publisher    = {Nature Publishing Group},
      reportid     = {FZJ-2019-02425},
      pages        = {855 - 860},
      year         = {2018},
      abstract     = {The two leading concepts for confining high-temperature
                      fusion plasmas are the tokamak and the stellarator. Tokamaks
                      are rotationally symmetric and use a large plasma current to
                      achieve confinement, whereas stellarators are
                      non-axisymmetric and employ three-dimensionally shaped
                      magnetic field coils to twist the field and confine the
                      plasma. As a result, the magnetic field of a stellarator
                      needs to be carefully designed to minimize the collisional
                      transport arising from poorly confined particle orbits,
                      which would otherwise cause excessive power losses at high
                      plasma temperatures. In addition, this type of transport
                      leads to the appearance of a net toroidal plasma current,
                      the so-called bootstrap current. Here, we analyse results
                      from the first experimental campaign of the Wendelstein 7-X
                      stellarator, showing that its magnetic-field design allows
                      good control of bootstrap currents and collisional
                      transport. The energy confinement time is among the best
                      ever achieved in stellarators, both in absolute figures
                      (τE > 100 ms) and relative to the stellarator
                      confinement scaling. The bootstrap current responds as
                      predicted to changes in the magnetic mirror ratio. These
                      initial experiments confirm several theoretically predicted
                      properties of Wendelstein 7-X plasmas, and already indicate
                      consistency with optimization measures.},
      cin          = {IEK-4},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000440583300022},
      doi          = {10.1038/s41567-018-0141-9},
      url          = {https://juser.fz-juelich.de/record/862061},
}