NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results
Identifieur interne :
000409 ( PascalFrancis/Curation );
précédent :
000408;
suivant :
000410
NSTX 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.
RBID : Pascal:12-0099491
Descripteurs français
English descriptors
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.
| pA |
| A01 | 01 | 1 | | @0 0920-3796 |
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| A02 | 01 | | | @0 FEDEEE |
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| A03 | | 1 | | @0 Fusion eng. des. |
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| A05 | | | | @2 86 |
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| A06 | | | | @2 9-11 |
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| A08 | 01 | 1 | ENG | @1 NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results |
|---|
| A09 | 01 | 1 | ENG | @1 Proceedings of the 26th Symposium on Fusion Technology (SOFT-26), Porto, Portugal, September 27-October 1, 2010. Part B |
|---|
| A11 | 01 | 1 | | @1 TITUS (P. H.) |
|---|
| A11 | 02 | 1 | | @1 AVASARALLA (S.) |
|---|
| A11 | 03 | 1 | | @1 BROOKS (A.) |
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| A11 | 04 | 1 | | @1 HATCHER (R.) |
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| A12 | 01 | 1 | | @1 VARANDAS (Carlos) @9 ed. |
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| A12 | 02 | 1 | | @1 GONCALVES (Bruno) @9 ed. |
|---|
| A12 | 03 | 1 | | @1 VARELA (Paulo) @9 ed. |
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| A14 | 01 | | | @1 Princeton Plasma Physics Laboratory, P.O. Box 451 @2 Princeton, NJ 08550 @3 USA @Z 1 aut. @Z 2 aut. @Z 3 aut. @Z 4 aut. |
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| A20 | | | | @1 1784-1790 |
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| A21 | | | | @1 2011 |
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| A23 | 01 | | | @0 ENG |
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| A43 | 01 | | | @1 INIST @2 12262F @5 354000506761480500 |
|---|
| A44 | | | | @0 0000 @1 © 2012 INIST-CNRS. All rights reserved. |
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| A45 | | | | @0 5 ref. |
|---|
| A47 | 01 | 1 | | @0 12-0099491 |
|---|
| A60 | | | | @1 P @2 C |
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| A61 | | | | @0 A |
|---|
| A64 | 01 | 1 | | @0 Fusion engineering and design |
|---|
| A66 | 01 | | | @0 NLD |
|---|
| C01 | 01 | | ENG | @0 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. |
|---|
| C02 | 01 | X | | @0 001D06D04E |
|---|
| C02 | 02 | X | | @0 230 |
|---|
| C03 | 01 | X | FRE | @0 Disruption @5 01 |
|---|
| C03 | 01 | X | ENG | @0 Disruption @5 01 |
|---|
| C03 | 01 | X | SPA | @0 Disrupción @5 01 |
|---|
| C03 | 02 | X | FRE | @0 Ecorceur @5 02 |
|---|
| C03 | 02 | X | ENG | @0 Divertor @5 02 |
|---|
| C03 | 02 | X | SPA | @0 Descortezador @5 02 |
|---|
| C03 | 03 | X | FRE | @0 Réacteur fusion nucléaire @5 03 |
|---|
| C03 | 03 | X | ENG | @0 Nuclear fusion reactor @5 03 |
|---|
| C03 | 03 | X | SPA | @0 Reactor fusión nuclear @5 03 |
|---|
| C03 | 04 | X | FRE | @0 Champ toroïdal @5 04 |
|---|
| C03 | 04 | X | ENG | @0 Toroidal field @5 04 |
|---|
| C03 | 04 | X | SPA | @0 Campo toroidal @5 04 |
|---|
| C03 | 05 | X | FRE | @0 Plasma @5 05 |
|---|
| C03 | 05 | X | ENG | @0 Plasma @5 05 |
|---|
| C03 | 05 | X | SPA | @0 Plasma @5 05 |
|---|
| C03 | 06 | X | FRE | @0 Faisceau particule neutre @5 06 |
|---|
| C03 | 06 | X | ENG | @0 Neutral beam @5 06 |
|---|
| C03 | 06 | X | SPA | @0 Haz partículas neutras @5 06 |
|---|
| C03 | 07 | X | FRE | @0 Modélisation @5 07 |
|---|
| C03 | 07 | X | ENG | @0 Modeling @5 07 |
|---|
| C03 | 07 | X | SPA | @0 Modelización @5 07 |
|---|
| C03 | 08 | X | FRE | @0 Tokamak @5 08 |
|---|
| C03 | 08 | X | ENG | @0 Tokamak @5 08 |
|---|
| C03 | 08 | X | SPA | @0 Tokamak @5 08 |
|---|
| C03 | 09 | X | FRE | @0 Courant Foucault @5 09 |
|---|
| C03 | 09 | X | ENG | @0 Eddy current @5 09 |
|---|
| C03 | 09 | X | SPA | @0 Corriente Foucault @5 09 |
|---|
| N21 | | | | @1 079 |
|---|
| N44 | 01 | | | @1 OTO |
|---|
| N82 | | | | @1 OTO |
|---|
|
|---|
| pR |
| A30 | 01 | 1 | ENG | @1 SOFT-26 Symposium on Fusion Technology @2 26 @3 Porto PRT @4 2010-09-27 |
|---|
|
|---|
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<idno type="ISSN">0920-3796</idno>
<imprint><date when="2011">2011</date>
</imprint><seriesStmt><title level="j" type="main">Fusion engineering and design</title>
<title level="j" type="abbreviated">Fusion eng. des.</title>
<idno type="ISSN">0920-3796</idno>
</seriesStmt><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>
</keywords><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>
<term>Courant Foucault</term>
</keywords><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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</fA01><fA02 i1="01"><s0>FEDEEE</s0>
</fA02><fA03 i2="1"><s0>Fusion eng. des.</s0>
</fA03><fA06><s2>9-11</s2>
</fA06><fA08 i1="01" i2="1" l="ENG"><s1>NSTX disruption simulations of detailed divertor and passive plate models by vector potential transfer from OPERA global analysis results</s1>
</fA08><fA09 i1="01" i2="1" l="ENG"><s1>Proceedings of the 26th Symposium on Fusion Technology (SOFT-26), Porto, Portugal, September 27-October 1, 2010. Part B</s1>
</fA09><fA11 i1="01" i2="1"><s1>TITUS (P. H.)</s1>
</fA11><fA11 i1="02" i2="1"><s1>AVASARALLA (S.)</s1>
</fA11><fA11 i1="03" i2="1"><s1>BROOKS (A.)</s1>
</fA11><fA11 i1="04" i2="1"><s1>HATCHER (R.)</s1>
</fA11><fA12 i1="01" i2="1"><s1>VARANDAS (Carlos)</s1>
<s9>ed.</s9>
</fA12><fA12 i1="02" i2="1"><s1>GONCALVES (Bruno)</s1>
<s9>ed.</s9>
</fA12><fA12 i1="03" i2="1"><s1>VARELA (Paulo)</s1>
<s9>ed.</s9>
</fA12><fA14 i1="01"><s1>Princeton Plasma Physics Laboratory, P.O. Box 451</s1>
<s2>Princeton, NJ 08550</s2>
<s3>USA</s3>
<sZ>1 aut.</sZ>
<sZ>2 aut.</sZ>
<sZ>3 aut.</sZ>
<sZ>4 aut.</sZ>
</fA14><fA20><s1>1784-1790</s1>
</fA20><fA21><s1>2011</s1>
</fA21><fA23 i1="01"><s0>ENG</s0>
</fA23><fA43 i1="01"><s1>INIST</s1>
<s2>12262F</s2>
<s5>354000506761480500</s5>
</fA43><fA44><s0>0000</s0>
<s1>© 2012 INIST-CNRS. All rights reserved.</s1>
</fA44><fA45><s0>5 ref.</s0>
</fA45><fA47 i1="01" i2="1"><s0>12-0099491</s0>
</fA47><fA60><s1>P</s1>
<s2>C</s2>
</fA60><fA64 i1="01" i2="1"><s0>Fusion engineering and design</s0>
</fA64><fA66 i1="01"><s0>NLD</s0>
</fA66><fC01 i1="01" l="ENG"><s0>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.</s0>
</fC01><fC02 i1="01" i2="X"><s0>001D06D04E</s0>
</fC02><fC02 i1="02" i2="X"><s0>230</s0>
</fC02><fC03 i1="01" i2="X" l="FRE"><s0>Disruption</s0>
<s5>01</s5>
</fC03><fC03 i1="01" i2="X" l="ENG"><s0>Disruption</s0>
<s5>01</s5>
</fC03><fC03 i1="01" i2="X" l="SPA"><s0>Disrupción</s0>
<s5>01</s5>
</fC03><fC03 i1="02" i2="X" l="FRE"><s0>Ecorceur</s0>
<s5>02</s5>
</fC03><fC03 i1="02" i2="X" l="ENG"><s0>Divertor</s0>
<s5>02</s5>
</fC03><fC03 i1="02" i2="X" l="SPA"><s0>Descortezador</s0>
<s5>02</s5>
</fC03><fC03 i1="03" i2="X" l="FRE"><s0>Réacteur fusion nucléaire</s0>
<s5>03</s5>
</fC03><fC03 i1="03" i2="X" l="ENG"><s0>Nuclear fusion reactor</s0>
<s5>03</s5>
</fC03><fC03 i1="03" i2="X" l="SPA"><s0>Reactor fusión nuclear</s0>
<s5>03</s5>
</fC03><fC03 i1="04" i2="X" l="FRE"><s0>Champ toroïdal</s0>
<s5>04</s5>
</fC03><fC03 i1="04" i2="X" l="ENG"><s0>Toroidal field</s0>
<s5>04</s5>
</fC03><fC03 i1="04" i2="X" l="SPA"><s0>Campo toroidal</s0>
<s5>04</s5>
</fC03><fC03 i1="05" i2="X" l="FRE"><s0>Plasma</s0>
<s5>05</s5>
</fC03><fC03 i1="05" i2="X" l="ENG"><s0>Plasma</s0>
<s5>05</s5>
</fC03><fC03 i1="05" i2="X" l="SPA"><s0>Plasma</s0>
<s5>05</s5>
</fC03><fC03 i1="06" i2="X" l="FRE"><s0>Faisceau particule neutre</s0>
<s5>06</s5>
</fC03><fC03 i1="06" i2="X" l="ENG"><s0>Neutral beam</s0>
<s5>06</s5>
</fC03><fC03 i1="06" i2="X" l="SPA"><s0>Haz partículas neutras</s0>
<s5>06</s5>
</fC03><fC03 i1="07" i2="X" l="FRE"><s0>Modélisation</s0>
<s5>07</s5>
</fC03><fC03 i1="07" i2="X" l="ENG"><s0>Modeling</s0>
<s5>07</s5>
</fC03><fC03 i1="07" i2="X" l="SPA"><s0>Modelización</s0>
<s5>07</s5>
</fC03><fC03 i1="08" i2="X" l="FRE"><s0>Tokamak</s0>
<s5>08</s5>
</fC03><fC03 i1="08" i2="X" l="ENG"><s0>Tokamak</s0>
<s5>08</s5>
</fC03><fC03 i1="08" i2="X" l="SPA"><s0>Tokamak</s0>
<s5>08</s5>
</fC03><fC03 i1="09" i2="X" l="FRE"><s0>Courant Foucault</s0>
<s5>09</s5>
</fC03><fC03 i1="09" i2="X" l="ENG"><s0>Eddy current</s0>
<s5>09</s5>
</fC03><fC03 i1="09" i2="X" l="SPA"><s0>Corriente Foucault</s0>
<s5>09</s5>
</fC03><fN21><s1>079</s1>
</fN21><fN44 i1="01"><s1>OTO</s1>
</fN44><fN82><s1>OTO</s1>
</fN82><pR><fA30 i1="01" i2="1" l="ENG"><s1>SOFT-26 Symposium on Fusion Technology</s1>
<s2>26</s2>
<s3>Porto PRT</s3>
<s4>2010-09-27</s4>
</fA30>
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