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@ARTICLE{Wu:38083,
      author       = {Wu, C. H. and Alessandrini, C. and Bonal, J. P. and Davis,
                      J. W. and Haasz, A. A. and Jacob, W. and Kallenbach, A. and
                      Keinonen, J. and Kornejew, P. and Moormann, R. and Philipps,
                      V. and Roth, J. and Scaffidi-Argentina, F. and Würz, H.},
      title        = {{P}rogress of the {E}uropean ${R}\&{D}$ on plasma-wall
                      interactions, neutron effects and tritium removal in {ITER}
                      plasma facing materials},
      journal      = {Fusion engineering and design},
      volume       = {56-57},
      issn         = {0920-3796},
      address      = {New York, NY [u.a.]},
      publisher    = {Elsevier},
      reportid     = {PreJuSER-38083},
      pages        = {179 - 187},
      year         = {2001},
      note         = {Record converted from VDB: 12.11.2012},
      abstract     = {In a next step D/T fusion device like ITER, an intense
                      neutron flux will be produced as a consequence of the
                      nuclear fusion reactions, The effects of the neutron induced
                      damage in the microstructure of the plasma-facing material
                      (PFM,) may significantly change the thermal properties and
                      the mechanical properties as well as the behaviour of the
                      swelling and the tritium retention in such materials. In
                      addition, a peak heat flux as high as 20 MW m(-2) and a
                      plasma flux of 10(18)-10(20) cm(-2) s(-1) are expected in
                      the divertor zone during the normal operation of the
                      reactor. The divertor materials have to withstand the
                      neutron damage, the high heat fluxes and the high erosion
                      caused by the interaction with the high flux plasma. The
                      sputtered particles are co-deposited with plasma, which may
                      contribute significantly to the total tritium inventory in
                      the PFM. Furthermore, the interaction of steam with the
                      sputtered particles (with usually high specific surfaces)
                      could produce large amounts of hydrogen. All of the above
                      topics represent critical issues for plasma performance,
                      safety and economy, as they could limit the use of some PFM
                      materials in next generation fusion devices. Therefore,
                      substantial $R\&D$ effort is needed to elucidate the effects
                      of the neutron induced damage on microstructure,
                      erosion/deposition, tritium retention and dust formation, as
                      well as on hydrogen production. In the framework of the
                      European Fusion $R\&D$ program, an extensive effort on
                      neutron effects of the material properties: namely, thermal
                      conductivity, mechanical properties, dimensional stability,
                      tritium trapping, erosion/deposition, co-deposition, dust
                      formation/removal, chemical reactivity with steam and
                      oxygen, outgassing, baking and tritium removal from PFM have
                      been undertaken during the past several years. In this
                      paper, the recent progress achieved within the European
                      Fusion $R\&D$ program and contributions to the development
                      of ITER PFMs are presented and critically discussed. (C)
                      2001 Elsevier Science B.V. All rights reserved.},
      keywords     = {J (WoSType)},
      cin          = {IPP-1 / IPP-2},
      ddc          = {620},
      cid          = {I:(DE-Juel1)VDB27 / I:(DE-Juel1)VDB28},
      pnm          = {Wandkonditionierung und Plasma-Wand-Prozesse},
      pid          = {G:(DE-Juel1)FUEK46},
      shelfmark    = {Nuclear Science $\&$ Technology},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000172978400019},
      doi          = {10.1016/S0920-3796(01)00255-1},
      url          = {https://juser.fz-juelich.de/record/38083},
}