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Effect of composition and surface characteristics on fuel retention in beryllium-containing co-deposited layers

  • Antti Hakola*
  • , Kalle Heinola
  • , Kenichiro Mizohata
  • , Jari Likonen
  • , Cristian Lungu
  • , Corneliu Porosnicu
  • , Eduardo Alves
  • , Rodrigo Mateus
  • , Iva Bogdanovic Radovic
  • , Zdravko Siketic
  • , Vincenc Nemanic
  • , Mohit Kumar
  • , Cedric Pardanaud
  • , Pascale Roubin
  • , WP PFC contributors
  • *Corresponding author for this work
    • International Atomic Energy Agency
    • University of Helsinki
    • National Institute for Lasers, Plasma and Radiation Physics (INFLPR)
    • Universidade de Lisboa
    • Ruđer Bošković Institute (IRB)
    • Jožef Stefan Institute
    • French National Center for Scientific Research (CNRS)

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    We have investigated retention of deuterium in beryllium-containing, laboratory-made films whose properties resemble co-deposits observed on JET-ILW or predicted for ITER. The samples were prepared using High Power Impulse Magnetron Sputtering and Thermo-ionic Vacuum Arc Deposition. We have observed that retention depends on the flux of D atoms on the growing film, but even more prominently on its composition, structure, and morphology. Especially, inclusion of carbon by 10-15 at% in the layers can increase retention by a factor of 2-10. This we attribute to increasing number of defects as well as aromatic and aliphatic C-D bonds in the samples. Other impurities do not significantly alter the D inventory while more D is retained in samples with rough or highly modified surfaces. Our results show that reproducing the reported D concentrations of ∼5 at% in JET-ILW-like deposits requires keeping the sample temperature at 100-200 °C during the production phase and optimizing the uniformity of deposition fluxes. Data from Be-D samples further indicate that fuel retention in more ITER-relevant co-deposits would be around 1-2 at%.

    Original languageEnglish
    Article number014038
    JournalPhysica Scripta
    Volume2020
    Issue numberT171
    DOIs
    Publication statusPublished - 1 Jan 2020
    MoE publication typeA1 Journal article-refereed
    Event17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands
    Duration: 20 May 201924 May 2019

    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 and 2019–2020 under grant agreement No. 633053. Work performed under EUROfusion WP PFC.

    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

    • Beryllium
    • Co-deposition
    • Fuel retention
    • H2020
    • Euratom

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