Tritium distributions on W-coated divertor tiles used in the third JET ITER-like wall campaign

Y. Hatano (Corresponding Author), S. E. Lee, Jari Likonen, Seppo Koivuranta, M. Hara, S. Masuzaki, N. Asakura, K. Isobe, T. Hayashi, J. Ikonen, A.M. Widdowson, X. Litaudon, S. Abduallev, M. Abhangi, P. Abreu, M. Afzal, K.M. Aggarwal, T. Ahlgren, J.H. Ahn, L. Aho-MantilaN. Aiba, M. Airila, R. Albanese, V. Aldred, D. Alegre, JET contributors

    Research output: Contribution to journalArticleScientificpeer-review

    10 Citations (Scopus)


    Tritium (T) distributions on tungsten (W)-coated plasma-facing tiles used in the third ITER-like wall campaign (2015–2016) of the Joint European Torus (JET) were examined by means of an imaging plate technique and β-ray induced x-ray spectrometry, and they were compared with the distributions after the second (2013–2014) campaign. Strong enrichment of T in beryllium (Be) deposition layers was observed after the second campaign. In contrast, T distributions after the third campaign was more uniform though Be deposition layers were visually recognized. The one of the possible explanations is enhanced desorption of T from Be deposition layers due to higher tile temperatures caused by higher energy input in the third campaign.
    Original languageEnglish
    Pages (from-to)258-261
    JournalNuclear Materials and Energy
    Publication statusPublished - 1 Jan 2019
    MoE publication typeA1 Journal article-refereed


    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 no. 633053 ) . The views and opinions expressed herein do not necessarily reflect those of the European Commission. 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.


    • tritium retention
    • radiation
    • deposition


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