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@ARTICLE{Rieth:904069,
      author       = {Rieth, M. and Dürrschnabel, M. and Bonk, S. and Antusch,
                      S. and Pintsuk, G. and Aiello, G. and Henry, J. and de
                      Carlan, Y. and Ghidersa, B.-E. and Neuberger, H. and Rey, J.
                      and Zeile, C. and De Wispelaere, N. and Simondon, E. and
                      Hoffmann, J.},
      title        = {{F}abrication routes for advanced first wall
                      design alternatives},
      journal      = {Nuclear fusion},
      volume       = {61},
      number       = {11},
      issn         = {0029-5515},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2021-05639},
      pages        = {116067 -},
      year         = {2021},
      abstract     = {In future nuclear fusion reactors, plasma facing components
                      have to sustain specific neutron damage. While the majority
                      of irradiation data provides a relatively clear picture of
                      the displacement damage, the effect of helium transmutation
                      is not yet explored in detail. Nevertheless, available
                      results from simulation experiments indicate that
                      $9\%-chromium$ steels will reach their operating limit as
                      soon as the growing helium bubbles extent a critical size.
                      At that point, the material would most probably fail due to
                      grain boundary embrittlement. In this contribution, we
                      present a strategy for the mitigation of the
                      before-mentioned problem using the following facts. (1) The
                      neutron dose and related transmutation rate decreases
                      quickly inside the first wall of the breeding blankets, that
                      is, only a plasma-near area is extremely loaded. (2)
                      Nanostructured oxide dispersion strengthened (ODS) steels
                      may have an enormous trapping effect on helium, which would
                      suppress the formation of large helium bubbles for a much
                      longer period. (3) Compared to conventional steels, ODS
                      steels also provide improved irradiation tensile ductility
                      and creep strength. Therefore, a design, based on the
                      fabrication of the plasma facing and highly neutron and heat
                      loaded parts of blankets by an ODS steel, while using
                      EUROFER97 for everything else, would extend the operating
                      time and enable a higher heat flux. Consequently, we (i)
                      developed and produced $14\%Cr$ ferritic ODS steel plates
                      and (ii) optimized and demonstrated a scalable industrial
                      production route. (iii) We fabricated a mock-up with five
                      cooling channels and a plated first wall of ODS steel, using
                      the same production processes as for a real component. (iv)
                      Finally, we performed high heat flux tests in the Helium
                      Loop Karlsruhe, applying a few hundred short and a few 2 h
                      long pulses, in which the operating temperature limit for
                      EUROFER97 (i.e. 550 °C) was finally exceeded by 100 K. (v)
                      Thereafter, microstructure and defect analyses did not
                      reveal critical defects or recognizable damage. Only a heat
                      affected zone in the EUROFER/ODS steel interface could be
                      detected. However, a solution to prohibit the formation of
                      such heat affected zones is given. These research
                      contributions demonstrate that the use of ODS steel is not
                      only feasible and affordable but could make a decisive
                      difference in the future design and performance of breeding
                      blankets},
      cin          = {IEK-4},
      ddc          = {620},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000708192300001},
      doi          = {10.1088/1741-4326/ac2523},
      url          = {https://juser.fz-juelich.de/record/904069},
}