NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results
Identifieur interne : 000C19 ( Main/Exploration ); précédent : 000C18; suivant : 000C20NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results
Auteurs : P. H. Titus [États-Unis] ; S. Avasaralla [États-Unis] ; A. Brooks [États-Unis] ; R. Hatcher [États-Unis]Source :
- Fusion engineering and design [ 0920-3796 ] ; 2011.
Descripteurs français
- Pascal (Inist)
English descriptors
- KwdEn :
Abstract
The national spherical torus experiment (NSTX) project is planning upgrades to the toroidal field, plasma current and pulse length. This involves the replacement of the centerstack, including the inner legs of the TF, OH, and inner PF coils. A second neutral beam will also be added. The increased performance of the upgrade requires qualification of the remaining components including the vessel, passive plates, and divertor for higher disruption loads. The hardware needing qualification is more complex than is typically accessible by large scale electromagnetic (EM) simulations of the plasma disruptions. The usual method is to include simplified representations of components in the large EM models and attempt to extract forces to apply to more detailed models. This paper describes a more efficient approach of combining comprehensive modeling of the plasma and tokamak conducting structures, using the 2D OPERA code, with much more detailed treatment of individual components using ANSYS electromagnetic and mechanical analysis. This capture local eddy currents and resulting loads in complex details, and allows efficient non-linear, and dynamic structural analyses. Published by Elsevier B.V.
Affiliations:
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Le document en format XML
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<profileDesc><textClass><keywords scheme="KwdEn" xml:lang="en"><term>Disruption</term>
<term>Divertor</term>
<term>Eddy current</term>
<term>Modeling</term>
<term>Neutral beam</term>
<term>Nuclear fusion reactor</term>
<term>Plasma</term>
<term>Tokamak</term>
<term>Toroidal field</term>
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<keywords scheme="Pascal" xml:lang="fr"><term>Disruption</term>
<term>Ecorceur</term>
<term>Réacteur fusion nucléaire</term>
<term>Champ toroïdal</term>
<term>Plasma</term>
<term>Faisceau particule neutre</term>
<term>Modélisation</term>
<term>Tokamak</term>
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<front><div type="abstract" xml:lang="en">The national spherical torus experiment (NSTX) project is planning upgrades to the toroidal field, plasma current and pulse length. This involves the replacement of the centerstack, including the inner legs of the TF, OH, and inner PF coils. A second neutral beam will also be added. The increased performance of the upgrade requires qualification of the remaining components including the vessel, passive plates, and divertor for higher disruption loads. The hardware needing qualification is more complex than is typically accessible by large scale electromagnetic (EM) simulations of the plasma disruptions. The usual method is to include simplified representations of components in the large EM models and attempt to extract forces to apply to more detailed models. This paper describes a more efficient approach of combining comprehensive modeling of the plasma and tokamak conducting structures, using the 2D OPERA code, with much more detailed treatment of individual components using ANSYS electromagnetic and mechanical analysis. This capture local eddy currents and resulting loads in complex details, and allows efficient non-linear, and dynamic structural analyses. Published by Elsevier B.V.</div>
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<name sortKey="Avasaralla, S" sort="Avasaralla, S" uniqKey="Avasaralla S" first="S." last="Avasaralla">S. Avasaralla</name>
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