% 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{Biel:844548,
      author       = {Biel, W. and Beckers, M. and Kemp, R. and Wenninger, R. and
                      Zohm, H.},
      title        = {{S}ystems code studies on the optimization of design
                      parameters for a pulsed {DEMO} tokamak reactor},
      journal      = {Fusion engineering and design},
      volume       = {123},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2018-01955},
      pages        = {206 - 211},
      year         = {2017},
      abstract     = {In the European strategy towards fusion power, a
                      demonstration tokamak fusion reactor (DEMO) is foreseen as
                      the next single step between ITER and a power plant. The
                      current baseline concept is a tokamak reactor with net
                      electrical output power of Pel ∼ 500 MW and plasma pulse
                      duration of tpulse ∼2 h. Systems codes are commonly used
                      in the design process as numerical tools for optimization
                      studies. The key performance data of the reactor such as Pel
                      and tpulse are depending on a variety of design and plasma
                      parameters. In the application of systems codes within this
                      multi-dimensional parameter space, a clear quantitative
                      understanding of the most suitable optimization criteria has
                      to be developed, and various physics and technology limits
                      should be obeyed to obtain meaningful results.In this work
                      we use a fusion reactor systems code to perform parameter
                      variations for a pulsed DEMO tokamak reactor. Various output
                      quantities are presented as a basis for the quantitative
                      assessment of the numerical results, and options for a
                      further development of the current DEMO baseline design are
                      proposed and briefly discussed.},
      cin          = {IEK-4},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174) / HITEC -
                      Helmholtz Interdisciplinary Doctoral Training in Energy and
                      Climate Research (HITEC) (HITEC-20170406)},
      pid          = {G:(DE-HGF)POF3-174 / G:(DE-Juel1)HITEC-20170406},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000418992000041},
      doi          = {10.1016/j.fusengdes.2017.01.009},
      url          = {https://juser.fz-juelich.de/record/844548},
}