Overview of JET results in support of the ITER physics basis

C. Cormezano (Corresponding author), Mervi Mantsinen, Tuomas Tala, JET Contributors

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific


    The JET experimental campaign has focused on studies in support of the ITER physics basis. An overview of the results obtained is given both for the reference ITER scenario, the ELMy H-mode, and for advanced scenarios which in JET are based on Internal Transport Barriers. JET studies for the ELMy H-mode have been instrumental for the definition of ITER-FEAT. Positive elongation and current scaling in the ITER scaling law have been confirmed, but the observed density scaling fits better a two term (core and edge) model. Significant progress in neo-classical tearing mode limits has been made showing that ITER operation seems to be optimised. Effective helium pumping and divertor enrichment is found to be well within ITER requirements. Target asymmetries and H-isotope retention are well simulated by modelling codes taking into account drift flows in the scrape-off plasmas. Striking improvements in fuelling effectiveness have been found with the new high field pellet launch facility. Good progress has been made on scenarios for achieving good confinement at high densities, both with RI modes and with high field side pellets. Significant development of advanced scenarios in view of their application to ITER has been achieved. Integrated advanced scenarios are in good progress with edge pressure control (impurity radiation). An access domain has been explored showing in particular that the power threshold increases with magnetic field but can be significantly reduced when Lower Hybrid current drive is used to produce target plasma with negative shear. The role of ion pressure peaking on MHD has been well documented. Lack of sufficient additional heating power and interaction with the septum at high beta prevents assessment of beta limits (steady plasmas achieved with βN up to 2.6). Plasmas with non-inductive current (INI/Ip=60%), well aligned with plasma current, high beta and good confinement have also been obtained.
    Original languageEnglish
    Title of host publication18. IAEA fusion energy conference
    Subtitle of host publicationProceedings
    PublisherInternational Atomic Energy Agency IAEA
    Number of pages16
    Publication statusPublished - 2000
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event18th IAEA Fusion Energy Conference - Sorrento, Italy
    Duration: 4 Oct 200010 Oct 2000

    Publication series

    SeriesConference & Symposium Papers


    Conference18th IAEA Fusion Energy Conference


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