JET contributions to ITER technology issues

C. Grisolia, S. Rosanvallon, P. Coad, N. Bekris, J. Braet, D. Brennan, B. Brichard, G. Counsell, C. Day, J. Likonen, G. Piazza, C. Poletiko, M. Rubel, Alexandre Semerok

    Research outputpeer-review

    Abstract

    The Joint European Torus (JET) fusion machine is the only device capable of operation with tritium and of handling Be and therefore is best suited to the study of tritium and fusion-related issues. A large variety of activities are performed within the JET fusion technology task force (FT-TF). In this paper, some topics such as erosion/deposition and material transport, characterisation of flakes and detritiation techniques are highlighted. Recent examples of results obtained on waste management studies are also given. Data on some ITER-relevant components that have been tested at JET, such as a pumping cryopanel and hardened optics fibers, are presented. In all fields, the work to be addressed in future JET work programmes is discussed.

    Original languageEnglish
    Title of host publicationFusion Engineering and Design
    Subtitle of host publicationProceedings of the Seventh International Symposium on Fusion Nuclear Technology: ISFNT-7 Part A
    PublisherElsevier B.V.
    Pages149-154
    Number of pages6
    Volume81 A
    Edition1-4
    DOIs
    StatePublished - Feb 2006
    Event7th International Symposium on Fusion Nuclear Technology - JAERI, Tokyo
    Duration: 22 May 200527 May 2005

    Publication series

    Namefusion engineering and design
    PublisherElsevier
    ISSN (Print)0920-3796

    Conference

    Conference7th International Symposium on Fusion Nuclear Technology
    Country/TerritoryJapan
    CityTokyo
    Period2005-05-222005-05-27

    ASJC Scopus subject areas

    • Civil and Structural Engineering
    • Nuclear Energy and Engineering
    • General Materials Science
    • Mechanical Engineering

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