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@ARTICLE{Hathiramani:858024,
      author       = {Hathiramani, D. and Ali, A. and Anda, G. and Barbui, T. and
                      Biedermann, C. and Charl, A. and Chauvin, D. and Czymek, G.
                      and Dhard, C. P. and Drewelow, P. and Dudek, A. and
                      Effenberg, F. and Ehrke, G. and Endler, M. and Ennis, D. A.
                      and Fellinger, J. and Ford, O. and Freundt, S. and Gradic,
                      D. and Grosser, K. and Harris, J. and Hölbe, H. and
                      Jakubowski, M. W. and Knaup, M. and Kocsis, G. and König,
                      R. and Krause, M. and Kremeyer, T. and Kornejew, P. and
                      Krychowiak, M. and Lambertz, H. T. and Jenzsch, H. and
                      Mayer, M. and Mohr, S. and Neubauer, O. and Otte, M. and
                      Perseo, V. and Pilopp, D. and Rudischhauser, L. and Schmitz,
                      O. and Schweer, B. and Schülke, M. and Stephey, L. and
                      Szepesi, T. and Terra, A. and Toth, M. and Wenzel, U. and
                      Wurden, G. A. and Zoletnik, S. and Pedersen, T. Sunn},
      title        = {{U}pgrades of edge, divertor and scrape-off layer
                      diagnostics of {W}7‐{X} for {OP}1.2},
      journal      = {Fusion engineering and design},
      volume       = {136},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2018-06968},
      pages        = {304 - 308},
      year         = {2018},
      abstract     = {Wendelstein 7-X (W7‐X) is the world’s largest
                      superconducting nuclear fusion experiment of the optimized
                      stellarator type. In the first Operation Phase (OP1.1)
                      helium and hydrogen plasmas were studied in limiter
                      configuration. The heating energy was limited to 4 MJ and
                      the main purpose of that campaign was the integral
                      commissioning of the machine and diagnostics, which was
                      achieved very successfully. Already from the beginning a
                      comprehensive set of diagnostics was available to study the
                      plasma. On the path towards high-power, high-performance
                      plasmas, W7‐X will be stepwise upgraded from an inertially
                      cooled (OP1.2, limited to 80 MJ) to an actively cooled
                      island divertor (OP2, 10 MW steady-state plasma
                      operation). The machine is prepared for OP1.2 with 10
                      inertially cooled divertor units, and the experimental
                      campaign has started recently.The paper describes a subset
                      of diagnostics which will be available for OP1.2 to study
                      the plasma edge, divertor and scrape-off layer physics
                      including those already available for OP1.1, plus
                      modifications, upgrades and new systems. The focus of this
                      summary will be on technical and engineering aspects, like
                      feasibility and assembly but also on reliability, thermal
                      loads and shielding against magnetic fields.},
      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:000452583700057},
      doi          = {10.1016/j.fusengdes.2018.02.013},
      url          = {https://juser.fz-juelich.de/record/858024},
}