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@ARTICLE{Weckmann:868240,
      author       = {Weckmann, A. and Petersson, P. and Rubel, M. and Ström, P.
                      and Kurki-Suonio, T. and Särkimäki, K. and Kirschner, A.
                      and Kreter, A. and Brezinsek, S. and Romazanov, J. and
                      Wienhold, P. and Pospieszczyk, A. and Hakola, A. and Airila,
                      M.},
      title        = {{R}eview on global migration, fuel retention and modelling
                      after {TEXTOR} decommission},
      journal      = {Nuclear materials and energy},
      volume       = {17},
      issn         = {2352-1791},
      address      = {Amsterdam [u.a.]},
      publisher    = {Elsevier},
      reportid     = {FZJ-2019-06800},
      pages        = {83 - 112},
      year         = {2018},
      abstract     = {Before decommissioning of the TEXTOR tokamak in 2013, the
                      machine was conditioned with a comprehensive migration
                      experiment where MoF6 and 15N2 were injected on the very
                      last operation day. Thereafter, all plasma-facing components
                      (PFCs) were available for extensive studies of both local
                      and global migration of impurities – Mo, W, Inconel alloy
                      constituents, 15 N, F – and fuel retention studies.
                      Measurements were performed on 140 limiter tiles out of 864
                      throughout the whole machine to map global transport. One
                      fifth of the introduced molybdenum could be found. Wherever
                      possible, the findings are compared to results obtained
                      previously in other machines. This review incorporates both
                      published and unpublished results from this TEXTOR study and
                      combines findings with analytical methods as well as
                      modelling results from two codes, ERO and ASCOT. The main
                      findings are:• Both local and global molybdenum transport
                      can be explained by toroidal plasma flow and drift. The
                      suggested transport scheme for molybdenum holds also for
                      other analysed species, namely tungsten from previous
                      experiments and medium-Z metals (Cr-Cu) introduced on
                      various occasions.• Analytical interpretation of several
                      deposition profile features is possible with basic
                      geometrical and plasma physics considerations. These are
                      deposition profiles on the collector probe, the lower part
                      of the inner bumper limiter, the poloidal cross-section of
                      the inner bumper limiter, and the poloidal limiter.• Any
                      deposition pattern found in this TEXTOR study, including
                      fuel retention, has neither poloidal nor toroidal symmetry,
                      which is often assumed when determining deposition profiles
                      on global scale.• Fuel retention is highly inhomogeneous
                      due to local variation of plasma parameters – by auxiliary
                      heating systems and impurity injection – and PFC
                      temperature.• Local modelling with ERO yields good
                      qualitative agreement but too high local deposition
                      efficiency.• Global modelling with ASCOT shows that the
                      radial electric field and source form have a high impact on
                      global deposition patterns, while toroidal flow has little
                      influence. Some of the experimental findings could be
                      reproduced. Still, qualitative differences between simulated
                      and experimental global deposition patterns remain.The
                      review closes with lessons learnt during this extensive
                      TEXTOR study which might be helpful for future scientific
                      exploitation of other tokamaks to be decommissioned.},
      cin          = {IEK-4},
      ddc          = {624},
      cid          = {I:(DE-Juel1)IEK-4-20101013},
      pnm          = {113 - Methods and Concepts for Material Development
                      (POF3-113)},
      pid          = {G:(DE-HGF)POF3-113},
      typ          = {PUB:(DE-HGF)16},
      UT           = {WOS:000454165000013},
      doi          = {10.1016/j.nme.2018.09.003},
      url          = {https://juser.fz-juelich.de/record/868240},
}