Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment
A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance ℓi, high elongation κ, and high toroidal and normalized beta ( βt and βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S...
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creator | Reusch, J. A. Bodner, G. M. Bongard, M. W. Burke, M. G. Fonck, R. J. Pachicano, J. L. Perry, J. M. Pierren, C. Rhodes, A. T. Richner, N. J. Rodriguez Sanchez, C. Schlossberg, D. J. Weberski, J. D. |
description | A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance
ℓi, high elongation
κ, and high toroidal and normalized beta (
βt and
βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low
ℓi. The low aspect ratio (
R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents (
IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high
βt plasmas. Equilibrium analyses indicate that
βt up to ∼100% is achieved. These high
βt discharges disrupt at the ideal no-wall
β limit at
βN∼7. |
doi_str_mv | 10.1063/1.5017966 |
format | Article |
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ℓi, high elongation
κ, and high toroidal and normalized beta (
βt and
βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low
ℓi. The low aspect ratio (
R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents (
IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high
βt plasmas. Equilibrium analyses indicate that
βt up to ∼100% is achieved. These high
βt discharges disrupt at the ideal no-wall
β limit at
βN∼7.</description><identifier>ISSN: 1070-664X</identifier><identifier>EISSN: 1089-7674</identifier><identifier>DOI: 10.1063/1.5017966</identifier><identifier>CODEN: PHPAEN</identifier><language>eng</language><publisher>United States: American Institute of Physics (AIP)</publisher><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY ; beta limit ; equilibrium reconstruction ; helicity injection ; magnetic reconnection ; spherical tokamaks ; tokamaks</subject><ispartof>Physics of plasmas, 2018-05, Vol.25 (5)</ispartof><rights>Author(s)</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><orcidid>0000-0002-3160-9746 ; 0000-0002-2828-9825 ; 0000-0003-3471-2586 ; 0000-0002-8424-9422 ; 0000-0001-7619-3724 ; 0000-0002-0725-5693 ; 0000-0003-2497-9172 ; 0000000155443915 ; 0000000280735714 ; 0000000284249422 ; 0000000334712586 ; 0000000207255693 ; 0000000231609746 ; 0000000176193724 ; 0000000324979172 ; 0000000287139448 ; 0000000294386762 ; 0000000256267914 ; 0000000228289825 ; 0000000171228609</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://pubs.aip.org/pop/article-lookup/doi/10.1063/1.5017966$$EHTML$$P50$$Gscitation$$H</linktohtml><link.rule.ids>230,314,780,784,794,885,4512,27924,27925,76384</link.rule.ids><backlink>$$Uhttps://www.osti.gov/servlets/purl/1433090$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Reusch, J. A.</creatorcontrib><creatorcontrib>Bodner, G. M.</creatorcontrib><creatorcontrib>Bongard, M. W.</creatorcontrib><creatorcontrib>Burke, M. G.</creatorcontrib><creatorcontrib>Fonck, R. J.</creatorcontrib><creatorcontrib>Pachicano, J. L.</creatorcontrib><creatorcontrib>Perry, J. M.</creatorcontrib><creatorcontrib>Pierren, C.</creatorcontrib><creatorcontrib>Rhodes, A. T.</creatorcontrib><creatorcontrib>Richner, N. J.</creatorcontrib><creatorcontrib>Rodriguez Sanchez, C.</creatorcontrib><creatorcontrib>Schlossberg, D. J.</creatorcontrib><creatorcontrib>Weberski, J. D.</creatorcontrib><creatorcontrib>Univ. of Wisconsin, Madison, WI (United States)</creatorcontrib><title>Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment</title><title>Physics of plasmas</title><description>A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance
ℓi, high elongation
κ, and high toroidal and normalized beta (
βt and
βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low
ℓi. The low aspect ratio (
R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents (
IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high
βt plasmas. Equilibrium analyses indicate that
βt up to ∼100% is achieved. These high
βt discharges disrupt at the ideal no-wall
β limit at
βN∼7.</description><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</subject><subject>beta limit</subject><subject>equilibrium reconstruction</subject><subject>helicity injection</subject><subject>magnetic reconnection</subject><subject>spherical tokamaks</subject><subject>tokamaks</subject><issn>1070-664X</issn><issn>1089-7674</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNp9kMtKAzEYhYMoWKsL3yC4FKbmMpPLUoo3KOpCQXAR_k4yNnaalEla7Gv5ID6TU1pw5-oc-L9z-DkInVMyokTwKzqqCJVaiAM0oETpQgpZHm69JIUQ5dsxOknpkxBSikoN0PtjDIUPdlVnv3btBtuu14BznMMC5njZQlpAwpBxcNAVq-DzBv98Z-x7aObws_uAtEp9oIveQovd19J1fuFCPkVHDbTJne11iF5vb17G98Xk6e5hfD0pIuVMFE5R1mjuFChC6BSYZlxqC1MJhMuqsY2jrJ42mglVgnJcVJI1lttKM6kV8CG62PXGlL1Jtc-untUxBFdnQ0vOiSY9dLmDtnfIPgaz7N-EbmMoMdvtDDX77f6D17H7A83SNvwXTpRw_A</recordid><startdate>201805</startdate><enddate>201805</enddate><creator>Reusch, J. A.</creator><creator>Bodner, G. 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A. ; Bodner, G. M. ; Bongard, M. W. ; Burke, M. G. ; Fonck, R. J. ; Pachicano, J. L. ; Perry, J. M. ; Pierren, C. ; Rhodes, A. T. ; Richner, N. J. ; Rodriguez Sanchez, C. ; Schlossberg, D. J. ; Weberski, J. D.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-o1326-e812f93e8a8001ba292379dab7a0375fdfe12cbf92684a8e36572fd3d592798a3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</topic><topic>beta limit</topic><topic>equilibrium reconstruction</topic><topic>helicity injection</topic><topic>magnetic reconnection</topic><topic>spherical tokamaks</topic><topic>tokamaks</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Reusch, J. A.</creatorcontrib><creatorcontrib>Bodner, G. M.</creatorcontrib><creatorcontrib>Bongard, M. W.</creatorcontrib><creatorcontrib>Burke, M. 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J.</au><au>Rodriguez Sanchez, C.</au><au>Schlossberg, D. J.</au><au>Weberski, J. D.</au><aucorp>Univ. of Wisconsin, Madison, WI (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment</atitle><jtitle>Physics of plasmas</jtitle><date>2018-05</date><risdate>2018</risdate><volume>25</volume><issue>5</issue><issn>1070-664X</issn><eissn>1089-7674</eissn><coden>PHPAEN</coden><abstract>A major goal of the spherical tokamak (ST) research program is accessing a state of low internal inductance
ℓi, high elongation
κ, and high toroidal and normalized beta (
βt and
βN) without solenoidal current drive. Local helicity injection (LHI) in the Pegasus ST [Garstka et al., Nucl. Fusion 46, S603 (2006)] provides non-solenoidally driven plasmas that exhibit these characteristics. LHI utilizes compact, edge-localized current sources for plasma startup and sustainment. It results in hollow current density profiles with low
ℓi. The low aspect ratio (
R0/a∼1.2) of Pegasus allows access to high κ and high normalized plasma currents (
IN=Ip/aBT>14). Magnetic reconnection during LHI provides auxiliary ion heating. Together, these features provide access to very high
βt plasmas. Equilibrium analyses indicate that
βt up to ∼100% is achieved. These high
βt discharges disrupt at the ideal no-wall
β limit at
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subjects | 70 PLASMA PHYSICS AND FUSION TECHNOLOGY beta limit equilibrium reconstruction helicity injection magnetic reconnection spherical tokamaks tokamaks |
title | Non-inductively driven tokamak plasmas at near-unity βt in the Pegasus toroidal experiment |
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