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

  • Y. Hatano*
  • , 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-Mantila
  • N. Aiba, M. Airila, R. Albanese, V. Aldred, D. Alegre, JET contributors
*Corresponding author for this work
    • University of Toyama
    • National Institutes of Natural Sciences - National Institute for Fusion Science
    • National Institutes for Quantum and Radiological Science and Technology (QST)
    • University of Helsinki
    • Culham Science Centre
    • Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA)
    • University of Naples Federico II
    • Laboratorio Nacional de Fusión (LNF)
    • National University of Distance Education

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    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
    Volume18
    DOIs
    Publication statusPublished - 1 Jan 2019
    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 under (Grant 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.

    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

    • tritium retention
    • radiation
    • deposition

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