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Current density limitation during disruptions due to plasma-sheaths

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F22%3A00558998" target="_blank" >RIV/61389021:_____/22:00558998 - isvavai.cz</a>

  • Alternative codes found

    RIV/00216208:11320/22:10456711

  • Result on the web

    <a href="https://iopscience.iop.org/article/10.1088/1741-4326/ac7656" target="_blank" >https://iopscience.iop.org/article/10.1088/1741-4326/ac7656</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1088/1741-4326/ac7656" target="_blank" >10.1088/1741-4326/ac7656</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Current density limitation during disruptions due to plasma-sheaths

  • Original language description

    The presented experimental study realized in the COMPASS tokamak demonstrates, for the first time, that the current density that flows from the plasma into the vacuum vessel during disruptions is limited by the ion particle flux. Such a limitation shows that, at least in COMPASS, the sheath that forms between the plasma and the first wall dominates the halo current flow. This observation is achieved by measuring simultaneously the ion saturation current with negatively biased Langmuir probes and the halo current with grounded probes to the vacuum vessel. These comparative measurements, which were never performed during disruptions in other machines, directly confirm that the halo current density remains below the ion particle flux in COMPASS. The study also shows, using Mirnov coils measurement, that the total electric current entering the wall grows with the plasma current while the current density obtained by Langmuir probes remains unaffected. This, together with the current density limitation, leads to a novel finding that the halo current width increases with the pre-disruptive plasma current, which limits the local forces. The new findings reported here could also provide potential constraints on the modeling of disruption-induced loads on future reactor scale tokamaks and motivation for further experiments on existing devices.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    10305 - Fluids and plasma physics (including surface physics)

Result continuities

  • Project

    Result was created during the realization of more than one project. More information in the Projects tab.

  • Continuities

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2022

  • Confidentiality

    S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Data specific for result type

  • Name of the periodical

    Nuclear Fusion

  • ISSN

    0029-5515

  • e-ISSN

    1741-4326

  • Volume of the periodical

    62

  • Issue of the periodical within the volume

    8

  • Country of publishing house

    AT - AUSTRIA

  • Number of pages

    6

  • Pages from-to

    086034

  • UT code for WoS article

    000816877400001

  • EID of the result in the Scopus database

    2-s2.0-85134174198