Loading of deuterium and helium by Pilot-PSI plasma and their detection by in-situ LIBS

K. Piip, H.J. van der Meiden, K. Bystrov, L. Hämarik, J. Karhunen, M. Aints, M. Laan, P. Paris, H. Seemen, Antti Hakola, S. Brezinsek

    Research output: Contribution to journalArticleScientificpeer-review

    11 Citations (Scopus)


    Laser-induced breakdown spectroscopy (LIBS) is a promising method for quantifying the fuel content of the plasma-facing components of ITER both in between plasma discharges (in-situ. ) and after maintenance operations. The aim of the present study is to test the applicability of in-situ LIBS for monitoring deuterium (D) and helium (He) content of W samples exposed to fusion relevant plasma fluxes in the linear plasma device Pilot-PSI. The D loading was performed during 1000 s of plasma exposure at low (200-300° C) surface temperatures. Despite of low intensity and noisy LIBS spectra, H and D lines, at 656.1 and 656.3 nm, respectively, could be fitted with Lorentzian contours and reliably resolved at 1.2 mbar background pressure of argon. In the case of He loading, the samples were also exposed to plasma during 1000 s while the surface temperature reached values up to 720° C at the center. Already at 10-2 mbar residual pressure of the device, the He I line at 587.6 nm was visible for the first 2-3 laser shots. We demonstrated that in-situ LIBS is a reliable method for detection of He and D retention in ITER-relevant materials. Nevertheless, for measuring relative and absolute concentrations of D and He in the ITER-relevant samples, further studies are needed.
    Original languageEnglish
    Pages (from-to)694-698
    JournalNuclear Materials and Energy
    Early online date2017
    Publication statusPublished - 1 Aug 2017
    MoE publication typeA1 Journal article-refereed
    Event22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22) - Rome, Italy
    Duration: 30 May 20163 Jun 2016


    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.


    • plasma surface interaction
    • LIBS
    • fuel retention
    • tungsten


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