Design of a Novel Variable Geometry Divertor for Tokamaks
The divertor is a key component of fusion reactors, allowing exhaust of gas, impurities, and helium ash to preserve plasma purity. The divertor geometry strongly affects plasma performance, and it is designed to be compatible with different plasma shapes in present-day fusion experiments. We present...
Gespeichert in:
| Veröffentlicht in: | IEEE transactions on plasma science 2022-09, Vol.50 (9), p.3238-3243 |
|---|---|
| Hauptverfasser: | , , , , |
| Format: | Artikel |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext bestellen |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | 3243 |
|---|---|
| container_issue | 9 |
| container_start_page | 3238 |
| container_title | IEEE transactions on plasma science |
| container_volume | 50 |
| creator | Xu, Chongdu Nagy, Alexander Bortolon, Alessandro Shafer, Morgan Laggner, Florian M. |
| description | The divertor is a key component of fusion reactors, allowing exhaust of gas, impurities, and helium ash to preserve plasma purity. The divertor geometry strongly affects plasma performance, and it is designed to be compatible with different plasma shapes in present-day fusion experiments. We present a novel concept for a variable geometry divertor, in which the divertor baffle tiles are reorientable by external actuation. Implementation of this concept in a medium-sized research tokamak would uniquely provide the flexibility to tailor divertor geometry to the plasma configuration and also enable study of the effect of divertor closure on plasma performance. To ensure compatibility with typical tokamak operations, the adjustable divertor must withstand the effects of significant mechanical and thermal stresses such as MW/m2-scale heat fluxes and large electromagnetic fields, e.g., disruption forces. The technological solutions for actuation mechanisms, cooling system, gas baffling and plasma-facing components are assessed. A functional reduced-scale model with movable outer divertor target baffle tiles is developed and the actuation mechanism is tested. |
| doi_str_mv | 10.1109/TPS.2022.3194847 |
| format | Article |
| fullrecord | <record><control><sourceid>proquest_RIE</sourceid><recordid>TN_cdi_crossref_primary_10_1109_TPS_2022_3194847</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><ieee_id>9861267</ieee_id><sourcerecordid>2718779345</sourcerecordid><originalsourceid>FETCH-LOGICAL-c313t-e6ca2dd356c597b4869fe36f11c7721d1bb9b6adc373e967648e3b98052bf73c3</originalsourceid><addsrcrecordid>eNo9kEtLw0AUhQdRsFb3gpug69SZuck8ltJqFYoKVrfDZHKj6SNTZ9JC_70pKS4uZ_Odw-Uj5JrREWNU38_fP0accj4CpjOVyRMyYBp0qkHmp2RAqYYUFINzchHjglKW5ZQPiJ5grL-bxFeJTV79DlfJlw21LVaYTNGvsQ37ZFLvMLQ-JFV3c7-0a7uMl-SssquIV8ccks-nx_n4OZ29TV_GD7PUAYM2ReEsL0vIhcu1LDIldIUgKsaclJyVrCh0IWzpQAJqIUWmEAqtaM6LSoKDIbntd31saxNd3aL7cb5p0LWGKSWU0h1010Ob4H-3GFuz8NvQdH8ZLpmSUkOWdxTtKRd8jAErswn12oa9YdQcLJrOojlYNEeLXeWmr9SI-I9rJRgXEv4AJO9ryw</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>2718779345</pqid></control><display><type>article</type><title>Design of a Novel Variable Geometry Divertor for Tokamaks</title><source>IEEE Electronic Library (IEL)</source><creator>Xu, Chongdu ; Nagy, Alexander ; Bortolon, Alessandro ; Shafer, Morgan ; Laggner, Florian M.</creator><creatorcontrib>Xu, Chongdu ; Nagy, Alexander ; Bortolon, Alessandro ; Shafer, Morgan ; Laggner, Florian M. ; Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</creatorcontrib><description>The divertor is a key component of fusion reactors, allowing exhaust of gas, impurities, and helium ash to preserve plasma purity. The divertor geometry strongly affects plasma performance, and it is designed to be compatible with different plasma shapes in present-day fusion experiments. We present a novel concept for a variable geometry divertor, in which the divertor baffle tiles are reorientable by external actuation. Implementation of this concept in a medium-sized research tokamak would uniquely provide the flexibility to tailor divertor geometry to the plasma configuration and also enable study of the effect of divertor closure on plasma performance. To ensure compatibility with typical tokamak operations, the adjustable divertor must withstand the effects of significant mechanical and thermal stresses such as MW/m2-scale heat fluxes and large electromagnetic fields, e.g., disruption forces. The technological solutions for actuation mechanisms, cooling system, gas baffling and plasma-facing components are assessed. A functional reduced-scale model with movable outer divertor target baffle tiles is developed and the actuation mechanism is tested.</description><identifier>ISSN: 0093-3813</identifier><identifier>EISSN: 1939-9375</identifier><identifier>DOI: 10.1109/TPS.2022.3194847</identifier><identifier>CODEN: ITPSBD</identifier><language>eng</language><publisher>New York: IEEE</publisher><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY ; Actuation ; Cooling systems ; Copper ; Divertor ; divertor closure ; Electromagnetic fields ; Exhaust gases ; Fusion reactors ; gas baffling ; Geometry ; Heat flux ; Heating systems ; Helium ; Impurities ; Plasma ; plasma-facing components ; Plasmas ; Scale models ; Shape ; Thermal stress ; Tiles ; Tokamak devices ; tokamak operations ; Tokamaks ; variable geometry</subject><ispartof>IEEE transactions on plasma science, 2022-09, Vol.50 (9), p.3238-3243</ispartof><rights>Copyright The Institute of Electrical and Electronics Engineers, Inc. (IEEE) 2022</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c313t-e6ca2dd356c597b4869fe36f11c7721d1bb9b6adc373e967648e3b98052bf73c3</cites><orcidid>0000-0003-2892-5091 ; 0000-0002-0094-0209 ; 0000-0002-8201-2528 ; 0000-0003-1601-2973 ; 0000-0001-9808-6305 ; 0000000200940209 ; 0000000328925091 ; 0000000282012528 ; 0000000198086305 ; 0000000316012973</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://ieeexplore.ieee.org/document/9861267$$EHTML$$P50$$Gieee$$H</linktohtml><link.rule.ids>230,314,780,784,796,885,27923,27924,54757</link.rule.ids><linktorsrc>$$Uhttps://ieeexplore.ieee.org/document/9861267$$EView_record_in_IEEE$$FView_record_in_$$GIEEE</linktorsrc><backlink>$$Uhttps://www.osti.gov/servlets/purl/1886889$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Xu, Chongdu</creatorcontrib><creatorcontrib>Nagy, Alexander</creatorcontrib><creatorcontrib>Bortolon, Alessandro</creatorcontrib><creatorcontrib>Shafer, Morgan</creatorcontrib><creatorcontrib>Laggner, Florian M.</creatorcontrib><creatorcontrib>Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</creatorcontrib><title>Design of a Novel Variable Geometry Divertor for Tokamaks</title><title>IEEE transactions on plasma science</title><addtitle>TPS</addtitle><description>The divertor is a key component of fusion reactors, allowing exhaust of gas, impurities, and helium ash to preserve plasma purity. The divertor geometry strongly affects plasma performance, and it is designed to be compatible with different plasma shapes in present-day fusion experiments. We present a novel concept for a variable geometry divertor, in which the divertor baffle tiles are reorientable by external actuation. Implementation of this concept in a medium-sized research tokamak would uniquely provide the flexibility to tailor divertor geometry to the plasma configuration and also enable study of the effect of divertor closure on plasma performance. To ensure compatibility with typical tokamak operations, the adjustable divertor must withstand the effects of significant mechanical and thermal stresses such as MW/m2-scale heat fluxes and large electromagnetic fields, e.g., disruption forces. The technological solutions for actuation mechanisms, cooling system, gas baffling and plasma-facing components are assessed. A functional reduced-scale model with movable outer divertor target baffle tiles is developed and the actuation mechanism is tested.</description><subject>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</subject><subject>Actuation</subject><subject>Cooling systems</subject><subject>Copper</subject><subject>Divertor</subject><subject>divertor closure</subject><subject>Electromagnetic fields</subject><subject>Exhaust gases</subject><subject>Fusion reactors</subject><subject>gas baffling</subject><subject>Geometry</subject><subject>Heat flux</subject><subject>Heating systems</subject><subject>Helium</subject><subject>Impurities</subject><subject>Plasma</subject><subject>plasma-facing components</subject><subject>Plasmas</subject><subject>Scale models</subject><subject>Shape</subject><subject>Thermal stress</subject><subject>Tiles</subject><subject>Tokamak devices</subject><subject>tokamak operations</subject><subject>Tokamaks</subject><subject>variable geometry</subject><issn>0093-3813</issn><issn>1939-9375</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><sourceid>RIE</sourceid><recordid>eNo9kEtLw0AUhQdRsFb3gpug69SZuck8ltJqFYoKVrfDZHKj6SNTZ9JC_70pKS4uZ_Odw-Uj5JrREWNU38_fP0accj4CpjOVyRMyYBp0qkHmp2RAqYYUFINzchHjglKW5ZQPiJ5grL-bxFeJTV79DlfJlw21LVaYTNGvsQ37ZFLvMLQ-JFV3c7-0a7uMl-SssquIV8ccks-nx_n4OZ29TV_GD7PUAYM2ReEsL0vIhcu1LDIldIUgKsaclJyVrCh0IWzpQAJqIUWmEAqtaM6LSoKDIbntd31saxNd3aL7cb5p0LWGKSWU0h1010Ob4H-3GFuz8NvQdH8ZLpmSUkOWdxTtKRd8jAErswn12oa9YdQcLJrOojlYNEeLXeWmr9SI-I9rJRgXEv4AJO9ryw</recordid><startdate>20220901</startdate><enddate>20220901</enddate><creator>Xu, Chongdu</creator><creator>Nagy, Alexander</creator><creator>Bortolon, Alessandro</creator><creator>Shafer, Morgan</creator><creator>Laggner, Florian M.</creator><general>IEEE</general><general>The Institute of Electrical and Electronics Engineers, Inc. (IEEE)</general><scope>97E</scope><scope>RIA</scope><scope>RIE</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7U5</scope><scope>8FD</scope><scope>L7M</scope><scope>OIOZB</scope><scope>OTOTI</scope><orcidid>https://orcid.org/0000-0003-2892-5091</orcidid><orcidid>https://orcid.org/0000-0002-0094-0209</orcidid><orcidid>https://orcid.org/0000-0002-8201-2528</orcidid><orcidid>https://orcid.org/0000-0003-1601-2973</orcidid><orcidid>https://orcid.org/0000-0001-9808-6305</orcidid><orcidid>https://orcid.org/0000000200940209</orcidid><orcidid>https://orcid.org/0000000328925091</orcidid><orcidid>https://orcid.org/0000000282012528</orcidid><orcidid>https://orcid.org/0000000198086305</orcidid><orcidid>https://orcid.org/0000000316012973</orcidid></search><sort><creationdate>20220901</creationdate><title>Design of a Novel Variable Geometry Divertor for Tokamaks</title><author>Xu, Chongdu ; Nagy, Alexander ; Bortolon, Alessandro ; Shafer, Morgan ; Laggner, Florian M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c313t-e6ca2dd356c597b4869fe36f11c7721d1bb9b6adc373e967648e3b98052bf73c3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>70 PLASMA PHYSICS AND FUSION TECHNOLOGY</topic><topic>Actuation</topic><topic>Cooling systems</topic><topic>Copper</topic><topic>Divertor</topic><topic>divertor closure</topic><topic>Electromagnetic fields</topic><topic>Exhaust gases</topic><topic>Fusion reactors</topic><topic>gas baffling</topic><topic>Geometry</topic><topic>Heat flux</topic><topic>Heating systems</topic><topic>Helium</topic><topic>Impurities</topic><topic>Plasma</topic><topic>plasma-facing components</topic><topic>Plasmas</topic><topic>Scale models</topic><topic>Shape</topic><topic>Thermal stress</topic><topic>Tiles</topic><topic>Tokamak devices</topic><topic>tokamak operations</topic><topic>Tokamaks</topic><topic>variable geometry</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Xu, Chongdu</creatorcontrib><creatorcontrib>Nagy, Alexander</creatorcontrib><creatorcontrib>Bortolon, Alessandro</creatorcontrib><creatorcontrib>Shafer, Morgan</creatorcontrib><creatorcontrib>Laggner, Florian M.</creatorcontrib><creatorcontrib>Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</creatorcontrib><collection>IEEE All-Society Periodicals Package (ASPP) 2005-present</collection><collection>IEEE All-Society Periodicals Package (ASPP) 1998-Present</collection><collection>IEEE Electronic Library (IEL)</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV - Hybrid</collection><collection>OSTI.GOV</collection><jtitle>IEEE transactions on plasma science</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>Xu, Chongdu</au><au>Nagy, Alexander</au><au>Bortolon, Alessandro</au><au>Shafer, Morgan</au><au>Laggner, Florian M.</au><aucorp>Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Design of a Novel Variable Geometry Divertor for Tokamaks</atitle><jtitle>IEEE transactions on plasma science</jtitle><stitle>TPS</stitle><date>2022-09-01</date><risdate>2022</risdate><volume>50</volume><issue>9</issue><spage>3238</spage><epage>3243</epage><pages>3238-3243</pages><issn>0093-3813</issn><eissn>1939-9375</eissn><coden>ITPSBD</coden><abstract>The divertor is a key component of fusion reactors, allowing exhaust of gas, impurities, and helium ash to preserve plasma purity. The divertor geometry strongly affects plasma performance, and it is designed to be compatible with different plasma shapes in present-day fusion experiments. We present a novel concept for a variable geometry divertor, in which the divertor baffle tiles are reorientable by external actuation. Implementation of this concept in a medium-sized research tokamak would uniquely provide the flexibility to tailor divertor geometry to the plasma configuration and also enable study of the effect of divertor closure on plasma performance. To ensure compatibility with typical tokamak operations, the adjustable divertor must withstand the effects of significant mechanical and thermal stresses such as MW/m2-scale heat fluxes and large electromagnetic fields, e.g., disruption forces. The technological solutions for actuation mechanisms, cooling system, gas baffling and plasma-facing components are assessed. A functional reduced-scale model with movable outer divertor target baffle tiles is developed and the actuation mechanism is tested.</abstract><cop>New York</cop><pub>IEEE</pub><doi>10.1109/TPS.2022.3194847</doi><tpages>6</tpages><orcidid>https://orcid.org/0000-0003-2892-5091</orcidid><orcidid>https://orcid.org/0000-0002-0094-0209</orcidid><orcidid>https://orcid.org/0000-0002-8201-2528</orcidid><orcidid>https://orcid.org/0000-0003-1601-2973</orcidid><orcidid>https://orcid.org/0000-0001-9808-6305</orcidid><orcidid>https://orcid.org/0000000200940209</orcidid><orcidid>https://orcid.org/0000000328925091</orcidid><orcidid>https://orcid.org/0000000282012528</orcidid><orcidid>https://orcid.org/0000000198086305</orcidid><orcidid>https://orcid.org/0000000316012973</orcidid><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext_linktorsrc |
| identifier | ISSN: 0093-3813 |
| ispartof | IEEE transactions on plasma science, 2022-09, Vol.50 (9), p.3238-3243 |
| issn | 0093-3813 1939-9375 |
| language | eng |
| recordid | cdi_crossref_primary_10_1109_TPS_2022_3194847 |
| source | IEEE Electronic Library (IEL) |
| subjects | 70 PLASMA PHYSICS AND FUSION TECHNOLOGY Actuation Cooling systems Copper Divertor divertor closure Electromagnetic fields Exhaust gases Fusion reactors gas baffling Geometry Heat flux Heating systems Helium Impurities Plasma plasma-facing components Plasmas Scale models Shape Thermal stress Tiles Tokamak devices tokamak operations Tokamaks variable geometry |
| title | Design of a Novel Variable Geometry Divertor for Tokamaks |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-11T07%3A02%3A28IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_RIE&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Design%20of%20a%20Novel%20Variable%20Geometry%20Divertor%20for%20Tokamaks&rft.jtitle=IEEE%20transactions%20on%20plasma%20science&rft.au=Xu,%20Chongdu&rft.aucorp=Princeton%20Plasma%20Physics%20Laboratory%20(PPPL),%20Princeton,%20NJ%20(United%20States)&rft.date=2022-09-01&rft.volume=50&rft.issue=9&rft.spage=3238&rft.epage=3243&rft.pages=3238-3243&rft.issn=0093-3813&rft.eissn=1939-9375&rft.coden=ITPSBD&rft_id=info:doi/10.1109/TPS.2022.3194847&rft_dat=%3Cproquest_RIE%3E2718779345%3C/proquest_RIE%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_pqid=2718779345&rft_id=info:pmid/&rft_ieee_id=9861267&rfr_iscdi=true |