% 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{Kasselmann:202020,
      author       = {Kasselmann, Stefan and Druska, Claudia and Herber, Stefan
                      and Jühe, Stephan and Keller, Florian and Lambertz, Daniela
                      and Li, Jingjing and Scholthaus, Sarah and Shi, Dunfu and
                      Xhonneux, Andre and Allelein, Hans-Josef},
      title        = {{S}tatus of the development of a fully integrated code
                      system for the simulation of high temperature reactor cores},
      journal      = {Nuclear engineering and design},
      volume       = {271},
      issn         = {0029-5493},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier Science},
      reportid     = {FZJ-2015-04309},
      pages        = {341 - 347},
      year         = {2014},
      abstract     = {The HTR code package (HCP) is a new code system, which
                      couples a variety of stand-alone codes for the simulation of
                      different aspects of HTR. HCP will allow the steady-state
                      and transient operating conditions of a 3D reactor core to
                      be simulated including new features such as spatially
                      resolved fission product release calculations or production
                      and transport of graphite dust. For this code the latest
                      programming techniques and standards are applied. As a first
                      step an object-oriented data model was developed which
                      features a high level of readability because it is based on
                      problem-specific data types like Nuclide, Reaction,
                      ReactionHandler, CrossSectionSet, etc. Those classes help to
                      encapsulate and therefore hide specific implementations,
                      which are not relevant with respect to physics. HCP will
                      make use of one consistent data library for which an
                      automatic generation tool was developed. The new data
                      library consists of decay information, cross sections,
                      fission yields, scattering matrices etc. for all available
                      nuclides (e.g. ENDF/B-VII.1). The data can be stored in
                      different formats such as binary, ASCII or XML. The new burn
                      up code TNT (Topological Nuclide Transmutation) applies
                      graph theory to represent nuclide chains and to minimize the
                      calculation effort when solving the burn up equations. New
                      features are the use of energy-dependent fission yields or
                      the calculation of thermal power for decay, fission and
                      capture reactions. With STACY (source term analysis code
                      system) the fission product release for steady state as well
                      as accident scenarios can be simulated for each fuel batch.
                      For a full-core release calculation several thousand fuel
                      elements are tracked while passing through the core. This
                      models the stochastic behavior of a pebble bed in a
                      realistic manner. In this paper we report on the current
                      status of the HCP and present first results, which prove the
                      applicability of the selected approach.},
      cin          = {IEK-6},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-6-20101013},
      pnm          = {141 - Safety Research for Nuclear Reactors (POF2-141) /
                      HITEC - Helmholtz Interdisciplinary Doctoral Training in
                      Energy and Climate Research (HITEC) (HITEC-20170406)},
      pid          = {G:(DE-HGF)POF2-141 / G:(DE-Juel1)HITEC-20170406},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000336348100057},
      doi          = {10.1016/j.nucengdes.2013.11.059},
      url          = {https://juser.fz-juelich.de/record/202020},
}