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@ARTICLE{Rieth:904071,
      author       = {Rieth, M. and Simondon, E. and Pintsuk, G. and Aiello, G.
                      and Henry, J. and Terentyev, D. and Puype, A. and Cristalli,
                      C. and Pilloni, L. and Tassa, O. and Klimenkov, M. and
                      Schneider, H.-C. and Fernandez, P. and Gräning, T. and
                      Chen, X. and Bhattacharya, A. and Reed, J. and Geringer, J.
                      W. and Sokolov, M. and Katoh, Y. and Snead, L.},
      title        = {{T}echnological aspects in blanket design: {E}ffects of
                      micro-alloying and thermo-mechanical treatments of
                      {EUROFER}97 type steels after neutron irradiation},
      journal      = {Fusion engineering and design},
      volume       = {168},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2021-05641},
      pages        = {112645 -},
      year         = {2021},
      note         = {kein Zugriff auf Postprint},
      abstract     = {Presently available data on neutron irradiation damage
                      raise doubts on the feasibility of using EUROFER97 steel for
                      a water-cooled starter blanket in a DEMO reactor, since the
                      ductile-to-brittle transition temperature (DBTT) increases
                      significantly for irradiation temperatures below 350°C. The
                      additional DBTT shift caused by H and He transmutation can
                      only be estimated based on very few results with
                      isotopically tailored EUROFER97 steel. Conservative
                      calculations show that the DBTT of EUROFER97 steel could
                      exceed the operating temperature in water-cooled starter
                      blankets within a relatively short time period. This paper
                      presents results from a EUROfusion funded irradiation
                      campaign that was performed in the High Flux Isotope Reactor
                      at Oak Ridge National Laboratory. The paper compares ten
                      newly developed reduced activation ferritic-martensitic
                      (RAFM) steels irradiated to a nominal dose of 2.5 dpa at
                      300°C. The post-irradiation experiments using Small
                      Specimen Test Technology included hardness, tensile, and
                      fracture mechanics tests combined with fractography and
                      microstructure analysis are presented. Results show that
                      micro-alloying EUROFER97-type steels influenced the
                      mechanical properties but a dominating impact on irradiation
                      damage resistance could not be identified. In contrast,
                      specific thermo-mechanical treatments lead to better DBTT
                      behavior. Discussion about irradiation response to heat
                      treatment conditions is also given. Despite requiring data
                      also at high dpa values, the results indicate that with
                      these modified materials an increased lifetime and
                      potentially also an increased operating temperature window
                      can be achieved compared to EUROFER97.},
      cin          = {IEK-4 / ZEA-1},
      ddc          = {530},
      cid          = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)ZEA-1-20090406},
      pnm          = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
      pid          = {G:(DE-HGF)POF4-134},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000670076200009},
      doi          = {10.1016/j.fusengdes.2021.112645},
      url          = {https://juser.fz-juelich.de/record/904071},
}