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@ARTICLE{Ogorodnikova:837282,
      author       = {Ogorodnikova, O. V. and Zhou, Z. and Sugiyama, K. and
                      Balden, M. and Pintsuk, G. and Gasparyan, Yu. and Efimov,
                      V.},
      title        = {{S}urface modification and deuterium retention in
                      reduced-activation steels under low-energy deuterium plasma
                      exposure. {P}art {II}: steels pre-damaged with 20 {M}e{V}
                      {W} ions and high heat flux},
      journal      = {Nuclear fusion},
      volume       = {57},
      number       = {3},
      issn         = {1741-4326},
      address      = {Vienna},
      publisher    = {IAEA},
      reportid     = {FZJ-2017-06251},
      pages        = {036011 -},
      year         = {2017},
      abstract     = {The reduced-activation ferritic/martensitic (RAFM) steels
                      including Eurofer (9Cr) and oxide dispersion strengthened
                      (ODS) steels by the addition of Y2O3 particles investigated
                      in Part I were pre-damaged either with 20 MeV W ions at room
                      temperature at IPP (Garching) or with high heat flux at FZJ
                      (Juelich) and subsequently exposed to low energy
                      (~20–200 eV per D) deuterium (D) plasma up to a fluence
                      of 2.9  ×  1025 D m−2 in the temperature range
                      from 290 K to 700 K. The pre-irradiation with 20 MeV W
                      ions at room temperature up to 1 displacement per atom (dpa)
                      has no noticeable influence on the steel surface morphology
                      before and after the D plasma exposure. The pre-irradiation
                      with W ions leads to the same concentration of deuterium in
                      all kinds of investigated steels, regardless of the presence
                      of nanoparticles and Cr content. It was found that (i) both
                      kinds of irradiation with W ions and high heat flux increase
                      the D retention in steels compared to undamaged steels and
                      (ii) the D retention in both pre-damaged and undamaged
                      steels decreases with a formation of surface roughness under
                      the irradiation of steels with deuterium ions with incident
                      energy which exceeds the threshold of sputtering. The
                      increase in the D retention in RAFM steels pre-damaged
                      either with W ions (damage up to ~3 µm) or high heat flux
                      (damage up to ~10 µm) diminishes with increasing the
                      temperature. It is important to mention that the near
                      surface modifications caused by either implantation of high
                      energy ions or a high heat flux load, significantly affect
                      the total D retention at low temperatures or low fluences
                      but have a negligible impact on the total D retention at
                      elevated temperatures and high fluences because, in these
                      cases, the D retention is mainly determined by bulk
                      diffusion.},
      cin          = {IEK-4},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {174 - Plasma-Wall-Interaction (POF3-174)},
      pid          = {G:(DE-HGF)POF3-174},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000391470100004},
      doi          = {10.1088/1741-4326/57/3/036011},
      url          = {https://juser.fz-juelich.de/record/837282},
}