Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F16%3A00460360" target="_blank" >RIV/61389021:_____/16:00460360 - isvavai.cz</a>

Result on the web

<a href="http://dx.doi.org/10.1088/0029-5515/56/6/066008" target="_blank" >http://dx.doi.org/10.1088/0029-5515/56/6/066008</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/0029-5515/56/6/066008" target="_blank" >10.1088/0029-5515/56/6/066008</a>

Result language

angličtina

Original language name

Three-dimensional modeling of plasma edge transport and divertor fluxes during application of resonant magnetic perturbations on ITER

Original language description

Results from three-dimensional modeling of plasma edge transport and plasma–wallninteractions during application of resonant magnetic perturbation (RMP) fields for control ofnedge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The fulln3D plasma fluid and kinetic neutral transport code EMC3-EIRENE is used for the modeling.nFour characteristic perturbed magnetic topologies are considered and discussed with referencento the axisymmetric case without RMP fields. Two perturbation field amplitudes at full andnhalf of the ITER ELM control coil current capability using the vacuum approximation arencompared to a case including a strongly screening plasma response. In addition, a vacuumnfield case at high q95 = 4.2 featuring increased magnetic shear has been modeled.nFormation of a three-dimensional plasma boundary is seen for all four perturbed magneticntopologies. The resonant field amplitudes and the effective radial magnetic field at the separatrixndefine the shape and extension of the 3D plasma boundary. Opening of the magnetic field linesnfrom inside the separatrix establishes scrape-off layer-like channels of direct parallel particlenand heat flux towards the divertor yielding a reduction of the main plasma thermal and particlenconfinement.This impact on confinement is most accentuated at full RMP current and is stronglynreduced when screened RMP fields are considered, as well as for the reduced coil current cases.

Czech name

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Czech description

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Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

BL - Plasma physics and discharge through gases

OECD FORD branch

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Project

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Continuities

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year

2016

Confidentiality

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

Name of the periodical

Nuclear Fusion

ISSN

0029-5515

e-ISSN

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Volume of the periodical

56

Issue of the periodical within the volume

6

Country of publishing house

AT - AUSTRIA

Number of pages

22

Pages from-to

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UT code for WoS article

000376446000012

EID of the result in the Scopus database

2-s2.0-84975518970