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@ARTICLE{Biel:907913,
      author       = {Biel, W. and Ariola, M. and Bolshakova, I. and Brunner, K.
                      J. and Cecconello, M. and Duran, I. and Franke, Th. and
                      Giacomelli, L. and Giannone, L. and Janky, F. and Krimmer,
                      A. and Luis, R. and Malaquias, A. and Marchiori, G. and
                      Marchuk, O. and Mazon, D. and Pironti, A. and Quercia, A.
                      and Rispoli, N. and Shawish, S. El and Siccinio, M. and
                      Silva, A. and Sozzi, C. and Tartaglione, G. and Todd, T. and
                      Treutterer, W. and Zohm, H.},
      title        = {{D}evelopment of a concept and basis for the {DEMO}
                      diagnostic and control system},
      journal      = {Fusion engineering and design},
      volume       = {179},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2022-02280},
      pages        = {113122 -},
      year         = {2022},
      abstract     = {An initial concept for the plasma diagnostic and control
                      $(D\&C)$ system has been developed as part of European
                      studies towards the development of a demonstration tokamak
                      fusion reactor (DEMO). The main objective is to develop a
                      feasible, integrated concept design of the DEMO $D\&C$
                      system that can provide reliable plasma control and high
                      performance (electricity output) over extended periods of
                      operation. While the fusion power is maximized when
                      operating near to the operational limits of the tokamak, the
                      reliability of operation typically improves when choosing
                      parameters significantly distant from these limits. In
                      addition to these conflicting requirements, the $D\&C$
                      development has to cope with strong adverse effects acting
                      on all in vessel components on DEMO (harsh neutron
                      environment, particle fluxes, temperatures, electromagnetic
                      forces, etc.). Moreover, space allocation and plasma access
                      are constrained by the needs for first wall integrity and
                      optimization of tritium breeding. Taking into account these
                      boundary conditions, the main DEMO plasma control issues
                      have been formulated, and a list of diagnostic systems and
                      channels needed for plasma control has been developed, which
                      were selected for their robustness and the required coverage
                      of control issues. For a validation and refinement of this
                      concept, simulation tools are being refined and applied for
                      equilibrium, kinetic and mode control studies.},
      cin          = {IEK-4},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000793698700005},
      doi          = {10.1016/j.fusengdes.2022.113122},
      url          = {https://juser.fz-juelich.de/record/907913},
}