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Experience of handling beryllium, tritium and activated components from JET ITER like wall

  • A. Widdowson
  • , A. Baron-Wiechec
  • , P. Batistoni
  • , E. Belonohy
  • , J.P. Coad
  • , P. Dinca
  • , D. Flammini
  • , F. Fox
  • , K. Heinola
  • , I. Jepu
  • , Jari Likonen
  • , S. Lilley
  • , C.P. Lungu
  • , G.F. Matthews
  • , J. Naish
  • , O. Pompilian
  • , C. Porosnicu
  • , M. Rubel
  • , R. Villari
  • , JET Contributors
    • Culham Science Centre
    • National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA)
    • Max-Planck-Institut für Plasmaphysik (IPP)
    • National Institute for Lasers, Plasma and Radiation Physics (INFLPR)
    • KTH Royal Institute of Technology
    • University of Helsinki

    Research output: Contribution to journalArticleScientificpeer-review

    Abstract

    JET components are removed periodically for surface analysis to assess material migration and fuel retention. This paper describes issues related to handling JET components and procedures for preparing samples for analysis; in particular a newly developed procedure for cutting beryllium tiles is presented. Consideration is also given to the hazards likely due to increased tritium inventory and material activation from 14 MeV neutrons following the planned TT and DT operations (DTE2) in 2017. Conclusions are drawn as to the feasibility of handling components from JET post DTE2.
    Original languageEnglish
    Number of pages11
    JournalPhysica Scripta
    Volume2016
    Issue numberT167
    DOIs
    Publication statusPublished - 2016
    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

    • beryllium
    • dose rate
    • JET
    • tritium

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