Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

S. E. Lee*, Y. Hatano, M. Hara, S. Masuzaki, M. Tokitani, M. Oyaizu, H. Kurotaki, D. Hamaguchi, H. Nakamura, N. Asakura, Y. Oya, Jari Likonen, A. Widdowson, S. Jachmich, K. Helariutta, M. Rubel

*Corresponding author for this work

    Research output: Contribution to journalArticleScientificpeer-review

    8 Citations (Scopus)

    Abstract

    Tritium (T) distribution on the plasma-facing surfaces (PFSs) and inside castellation of Be limiter tiles from the JET tokamak with the ITER-like wall (ILW) was analyzed using imaging plate (IP) technique and β-ray induced X-ray spectrometry (BIXS). Regarding to PFSs, the outer poloidal limiter (OPL) showed significantly higher T concentrations than the inner wall guard limiter (IWGL) and upper dump plate (DP). The concentration of T on OPL was high at the central part. However, deuterium (D) and metallic impurities showed maximum concentration at the edges. This difference in distributions indicated different deposition and retention mechanisms between T and D. In contrast, deposition profiles of T concentrations on the castellated surfaces extended up to ∼ 5 mm into the gap, i.e. were similar to those of D and metallic impurities found by ion beam analysis.
    Original languageEnglish
    Article number111959
    JournalFusion Engineering and Design
    Volume160
    Early online date1 Sept 2020
    DOIs
    Publication statusPublished - Nov 2020
    MoE publication typeA1 Journal article-refereed

    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. The study was supported by JSPS KAKENHI (Grant no. JP26289353), the ITER Broader Approach Activities, and the National Institute for Fusion Research (NIFS) as a part of PWI Collaboration.

    Keywords

    • Beryllium
    • ITER-like wall
    • Joint European Torus
    • Radiography
    • Tritium analysis

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