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Erosion and deposition in the JET divertor during the second ITER-like wall campaign

  • M. Mayer*
  • , Seppo Koivuranta
  • , Jari Likonen
  • , JET Contributors
  • *Corresponding author for this work
    • Max-Planck-Institut für Plasmaphysik (IPP)
    • National Research Nuclear University (MEPhI)
    • Culham Science Centre
    • University of Helsinki
    • National Institute for Lasers, Plasma and Radiation Physics (INFLPR)

    Research output: Contribution to journalArticle in a proceedings journalScientificpeer-review

    Abstract

    Erosion of plasma-facing materials and successive transport and redeposition of eroded material are crucial processes determining the lifetime of plasma-facing components and the trapped tritium inventory in redeposited material layers. Erosion and deposition in the JET divertor were studied during the second JET ITER-like wall campaign ILW-2 in 2013-2014 by using a poloidal row of specially prepared divertor marker tiles including the tungsten bulk tile 5. The marker tiles were analyzed using elastic backscattering with 3-4.5 MeV incident protons and nuclear reaction analysis using 0.8-4.5 MeV 3He ions before and after the campaign. The erosion/deposition pattern observed during ILW-2 is qualitatively comparable to the first campaign ILW-1 in 2011-2012: deposits consist mainly of beryllium with 5-20 at.% of carbon and oxygen and small amounts of Ni and W. The highest deposition with deposited layer thicknesses up to 30 μm per campaign is still observed on the upper and horizontal parts of the inner divertor. Outer divertor tiles 5, 6, 7 and 8 are net W erosion areas. The observed D inventory is roughly comparable to the inventory observed during ILW-1. The results obtained during ILW-2 therefore confirm the positive results observed in ILW-1 with respect to reduced material deposition and hydrogen isotopes retention in the divertor.

    Original languageEnglish
    Article number014058
    JournalPhysica Scripta
    Volume2017
    Issue numberT170
    DOIs
    Publication statusPublished - 1 Dec 2017
    MoE publication typeA4 Article in a conference publication
    Event16th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2017 - Neuss/Dusseldorf, Germany
    Duration: 16 May 201719 May 2017

    Funding

    This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement no. 633053.

    UN SDGs

    This output contributes to the following UN Sustainable Development Goals (SDGs)

    1. SDG 7 - Affordable and Clean Energy
      SDG 7 Affordable and Clean Energy

    Keywords

    • Divertor
    • JET-ILW
    • Material deposition
    • Material erosion
    • Surface analysis

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