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Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

  • Y. Torikai*
  • , G. Kikuchi
  • , A. Owada
  • , Suguru Masuzaki
  • , Teppei Otsuka
  • , N. Ashikawa
  • , M. Yajima
  • , Masayuki Tokitani
  • , Yasuhisa Oya
  • , S.E. Lee
  • , Y. Hatano
  • , N. Asakura
  • , T. Hayashi
  • , Makoto Oyaidzu
  • , Jari Likonen
  • , A. Widdowson
  • , Marek Rubel
  • *Corresponding author for this work
  • Ibaraki University
  • National Institute for Fusion Science
  • Kindai University
  • The Graduate University for Advanced Studies (SOKENDAI)
  • Shizuoka University
  • University of Toyama
  • National Institutes for Quantum and Radiological Science and Technology (QST)
  • Culham Science Centre
  • KTH Royal Institute of Technology
  • Uppsala University

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5–12 kBq cm−2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW.
Original languageEnglish
Article number 016032
JournalNuclear Fusion
Volume64
Issue number1
DOIs
Publication statusPublished - Jan 2024
MoE publication typeA1 Journal article-refereed

Funding

This work was carried out within the framework of the Broader Approach DEMO R&D Activity and the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200—EUROfusion). Views and opinions expressed are however those of the author(s) only and do not necessarily reflect those of the European Union or the European Commission. Neither the European Union nor EAN Commission can be held responsible for them. The work has been supported by the Swedish Research Council (VR) (Grants 2015–04844 and 2016–05380) and the UK EPSRC Energy Programme (Grant Number EP/W006839/1). This work was performed with the support and under the auspices of the NIFS Collaboration Research Program (NIFS21KLPF082).

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
  • JET
  • divertor
  • dust
  • ITER like wall

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