Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification

Brezinsek, S. and Coenen, J. W. and Schwarz-Selinger, T. and Schmid, K. and Kirschner, A. and Hakola, A. and Tabares, F.L. and Ben Yaala, Marwa (2017) Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification. Nuclear Fusion, 57 (11). 116041. ISSN 0029-5515 (https://doi.org/10.1088/1741-4326/aa796e)

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Abstract

The provision of a particle and power exhaust solution which is compatible with first-wall components and edge-plasma conditions is a key area of present-day fusion research and mandatory for a successful operation of ITER and DEMO. The work package plasma-facing components (WP PFC) within the European fusion programme complements with laboratory experiments, i.e. in linear plasma devices, electron and ion beam loading facilities, the studies performed in toroidally confined magnetic devices, such as JET, ASDEX Upgrade, WEST etc. The connection of both groups is done via common physics and engineering studies, including the qualification and specification of plasma-facing components, and by modelling codes that simulate edge-plasma conditions and the plasma–material interaction as well as the study of fundamental processes. WP PFC addresses these critical points in order to ensure reliable and efficient use of conventional, solid PFCs in ITER (Be and W) and DEMO (W and steel) with respect to heat-load capabilities (transient and steady-state heat and particle loads), lifetime estimates (erosion, material mixing and surface morphology), and safety aspects (fuel retention, fuel removal, material migration and dust formation) particularly for quasi-steady-state conditions. Alternative scenarios and concepts (liquid Sn or Li as PFCs) for DEMO are developed and tested in the event that the conventional solution turns out to not be functional. Here, we present an overview of the activities with an emphasis on a few key results: (i) the observed synergistic effects in particle and heat loading of ITER-grade W with the available set of exposition devices on material properties such as roughness, ductility and microstructure; (ii) the progress in understanding of fuel retention, diffusion and outgassing in different W-based materials, including the impact of damage and impurities like N; and (iii), the preferential sputtering of Fe in EUROFER steel providing an in situ W surface and a potential first-wall solution for DEMO.

ORCID iDs

Brezinsek, S., Coenen, J. W., Schwarz-Selinger, T., Schmid, K., Kirschner, A., Hakola, A., Tabares, F.L. and Ben Yaala, Marwa ORCID logoORCID: https://orcid.org/0000-0002-6754-0875;
  • Item type:Article
    ID code:84096
    Dates:
    Date
    Event
    18 August 2017
    Published
    14 June 2017
    Accepted
    Notes:S. Brezinsek et al 2017 Nucl. Fusion 57 116041 DOI 10.1088/1741-4326/aa796e
    Subjects:Science > Physics
    Department:Faculty of Engineering > Biomedical Engineering
    Depositing user: Pure Administrator
    Date deposited:09 Feb 2023 10:16
    Last modified:11 Nov 2024 13:45
    URI:https://strathprints.strath.ac.uk/id/eprint/84096
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