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@ARTICLE{Kasselmann:837302,
      author       = {Kasselmann, S. and Schitthelm, O. and Tantillo, F. and
                      Scholthaus, S. and Rössel, C. and Allelein, H.-J.},
      title        = {{D}evelopment of a new nuclide generation and depletion
                      code using a topological solver based on graph theory},
      journal      = {Nuclear engineering and design},
      volume       = {306},
      issn         = {0029-5493},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier Science},
      reportid     = {FZJ-2017-06267},
      pages        = {154 - 159},
      year         = {2016},
      abstract     = {The problem of calculating the amounts of a coupled nuclide
                      system varying with time especially when exposed to a
                      neutron flux is a well-known problem and has been addressed
                      by a number of computer codes. These codes cover a broad
                      spectrum of applications, are based on comprehensive
                      validation work and are therefore justifiably renowned among
                      their users. However, due to their long development history,
                      they are lacking a modern interface, which impedes a fast
                      and robust internal coupling to other codes applied in the
                      field of nuclear reactor physics. Therefore a project has
                      been initiated to develop a new object-oriented nuclide
                      transmutation code. It comprises an innovative solver based
                      on graph theory, which exploits the topology of nuclide
                      chains and therefore speeds up the calculation scheme.
                      Highest priority has been given to the existence of a
                      generic software interface well as an easy handling by
                      making use of XML files for the user input. In this paper we
                      report on the status of the code development and present
                      first benchmark results, which prove the applicability of
                      the selected approach.},
      cin          = {IEK-6},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-6-20101013},
      pnm          = {162 - Reactor Safety (POF3-162) / HITEC - Helmholtz
                      Interdisciplinary Doctoral Training in Energy and Climate
                      Research (HITEC) (HITEC-20170406)},
      pid          = {G:(DE-HGF)POF3-162 / G:(DE-Juel1)HITEC-20170406},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000383292400019},
      doi          = {10.1016/j.nucengdes.2016.03.016},
      url          = {https://juser.fz-juelich.de/record/837302},
}