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Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation

  1. 1.
    SYSNO ASEP0399688
    Document TypeC - Proceedings Paper (int. conf.)
    R&D Document TypeThe record was not marked in the RIV
    TitleProgress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation
    Author(s) Loarte, A. (FR)
    Huijsmans, G. (FR)
    Futatani, S. (FR)
    Campbell, D.J. (FR)
    Casper, T. (FR)
    Daly, E. (FR)
    Gribov, Y. (FR)
    Pitts, R.A. (FR)
    Lisgo, S. (FR)
    Sashala Naik, A. (FR)
    Baylor, L.R. (US)
    Evans, T.E. (US)
    Orlov, D.M. (US)
    Wingen, A. (US)
    Schmitz, O. (DE)
    Frerichs, H. (DE)
    Kischner, A. (DE)
    Laengner, R. (DE)
    Saibene, G. (ES)
    Bécoulet, M. (FR)
    Cahyna, Pavel (UFP-V) RID
    Kavin, A. (RU)
    Source Title24th IAEA Fusion Energy Conference – Programme, Abstracts,. - San Diego : International Atomic Energy Agency (IAEA), 2013 - ISBN N
    Pagesitr/1-2-itr/1-2
    Number of pages8 s.
    Publication formOnline - E
    ActionIAEA Fusion Energy Conference/24./
    Event date08.10.2012-13.10.2012
    VEvent locationSan Diego
    CountryUS - United States
    Event typeWRD
    Languageeng - English
    CountryUS - United States
    KeywordsEdge localized mode ; ITER
    Subject RIVBL - Plasma and Gas Discharge Physics
    Institutional supportUFP-V - RVO:61389021
    AnnotationProgress in the definition of the requirements for ELM control and the application of ELM control methods both for high fusion performance DT operation and non-active low current operation in ITER is described. Uncontrolled ELMs for low plasma current H-modes are not likely to lead to damage to the W divertor target. Despite this, some level of ELM control is expected to be required in ITER to prevent an excessive contamination of the plasma by W which could eventually lead to an increased disruptivity. The evaluation of the capabilities of the ELM control coil system in ITER for ELM suppression (in the vacuum approximation) is presented as well as the consequences for the spatial distribution of the power fluxes at the divertor. The feasibility of the use of the in-vessel vertical stability coils for ELM control in low plasma current H-modes in ITER is described.
    WorkplaceInstitute of Plasma Physics
    ContactVladimíra Kebza, kebza@ipp.cas.cz, Tel.: 266 052 975
    Year of Publishing2014
Number of the records: 1  

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