% IMPORTANT: The following is UTF-8 encoded.  This means that in the presence
% of non-ASCII characters, it will not work with BibTeX 0.99 or older.
% Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or
% “biber”.

@ARTICLE{Ariola:864599,
      author       = {Ariola, M. and Pironti, A. and Ambrosino, R. and Mattei, M.
                      and Biel, W. and Franke, T.},
      title        = {{S}imulation of magnetic control of the plasma shape on the
                      {DEMO} tokamak},
      journal      = {Fusion engineering and design},
      volume       = {146},
      number       = {Part A},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2019-04309},
      pages        = {728 - 731},
      year         = {2019},
      abstract     = {About $85\%$ of the primary energy is currently obtained
                      from fossil sources. In the next future, nuclear fusion can
                      significantly contribute to energy production: the fuel is
                      in principle unlimited and radioactive waste are short
                      lived. Next steps in fusion research are represented by the
                      two tokamaks ITER, which is under construction, and DEMO,
                      which is in its conceptual design phase. In this paper we
                      focus on a specific aspect of DEMO design, that is indeed
                      crucial for tokamak safe operation: plasma vertical and
                      shape control. It is well known that a plasma with elongated
                      cross-section exhibits a vertical instability that needs to
                      be feedback controlled. Typically on operating tokamaks, and
                      in ITER, this task is accomplished using in-vessel actuator
                      coils. Since in the present DEMO design these coils are not
                      foreseen, hereafter we assumed that all the actuator coils,
                      located outside the vessel, are used at the same time to
                      guarantee both vertical stabilization and shape control,
                      resorting to a suitable geometric decoupling. The
                      performance of the controller is shown in simulation using a
                      nonlinear evolution code during a plasma H-L
                      back-transition.},
      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:000488307400162},
      doi          = {10.1016/j.fusengdes.2019.01.065},
      url          = {https://juser.fz-juelich.de/record/864599},
}