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@ARTICLE{Allelein:888758,
      author       = {Allelein, Hans-Josef and Reinecke, Ernst-Arndt and Kelm,
                      Stephan and Klauck, Michael},
      title        = {{S}evere accident related activities of the research center
                      {J}ülich/{G}ermany},
      journal      = {International Journal of Advanced Nuclear Reactor Design
                      and Technology},
      volume       = {2},
      issn         = {2468-6050},
      publisher    = {KeAi Communications Co., Ltd.},
      reportid     = {FZJ-2020-05187},
      pages        = {131-143},
      year         = {2020},
      abstract     = {In Germany, the Helmholtz Association’s program NUSAFE
                      (Nuclear Waste Management, Safety and Radiation Research)
                      tackles the scientific challenges for the safety of nuclear
                      reactors in the key areas of design basis (DBA) and beyond
                      design basis accidents (BDBA). As one of the three research
                      centers in NUSAFE, the $R\&D$ activities at
                      Forschungszentrum Jülich (FZJ) focus on containment
                      phenomena and processes during severe accidents. FZJ
                      supports international efforts to further develop
                      computational methods and tools by providing worldwide
                      unique facilities in the field of wall condensation, aerosol
                      behavior and hydrogen mitigation for advanced code
                      development and validation. Development of computational
                      fluid dynamics (CFD) tools for containment application aims
                      at the integration of existing knowledge and the transfer of
                      research results into application. All research activities
                      are integrated into international collaborations and
                      projects.},
      cin          = {IEK-6},
      cid          = {I:(DE-Juel1)IEK-6-20101013},
      pnm          = {162 - Reactor Safety (POF3-162)},
      pid          = {G:(DE-HGF)POF3-162},
      typ          = {PUB:(DE-HGF)16},
      doi          = {10.1016/j.jandt.2020.12.001},
      url          = {https://juser.fz-juelich.de/record/888758},
}