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JET contribution to ITER fuel cycle issues

  • C. Grisolia*
  • , N. Bekris
  • , Jari Likonen
  • , P. Coad
  • , A. Semerok
  • , D. Brennan
  • , G. Piazza
  • , S. Rosanvallon
  • , JET-EFDA contributors
  • *Corresponding author for this work
    • CEA Cadarache
    • Forschungszentrum Karlsruhe (FZK)
    • National Nuclear Laboratory (Abingdon)
    • CEA Saclay

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and Be, which makes it best suited to study ITER relevant issues. A large variety of activities are performed within the JET fusion technology task force. In this paper, some topics, such as erosion/deposition and material transport, flakes characterization and detritiation techniques, are highlighted. Recent results obtained using a pumping cryopanel and on plasma facing component (PFC) characterization, are given. Finally, issues that will be addressed in the forthcoming JET work-programme are presented, such as a beryllium main wall for JET and in situ laser detritiation.
    Original languageEnglish
    Pages (from-to)679-683
    JournalFusion Engineering and Design
    Volume75-79
    DOIs
    Publication statusPublished - 2005
    MoE publication typeA1 Journal article-refereed

    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

    • detritiation techniques
    • fusion cycle
    • ITER
    • JET
    • fusion energy

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