Application of high temperature superconductors for fusion
The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70 kA HTS current lead demonstrator was designed, fabricated and successfully test...
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description | The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70
kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2
kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads @ 20
kA and 6 leads @ 25.7
kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads.
With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65
K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20
kA at high fields well above 10
T. The high field rules BiSCCO superconductors out at temperatures above 50
K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for DEMO. KIT has already demonstrated a scalable concept using RE-123 HTS tapes that are assembled to Roebel type conductors. This concept can be expanded to form Rutherford cables as starting point for a development of a high current fusion cable. The status and prospect of using HTS conductors for fusion is discussed. |
doi_str_mv | 10.1016/j.fusengdes.2010.11.018 |
format | Article |
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kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2
kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads @ 20
kA and 6 leads @ 25.7
kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads.
With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65
K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20
kA at high fields well above 10
T. The high field rules BiSCCO superconductors out at temperatures above 50
K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for DEMO. KIT has already demonstrated a scalable concept using RE-123 HTS tapes that are assembled to Roebel type conductors. This concept can be expanded to form Rutherford cables as starting point for a development of a high current fusion cable. The status and prospect of using HTS conductors for fusion is discussed.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2010.11.018</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Cables ; Coils ; Conductors ; Controled nuclear fusion plants ; Current leads ; DEMO ; Design engineering ; Economics ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fusion magnets ; High current ; High temperature superconductor ; High temperature superconductors ; Installations for energy generation and conversion: thermal and electrical energy ; ITER ; Superconductors ; W7-X</subject><ispartof>Fusion engineering and design, 2011-10, Vol.86 (6), p.1365-1368</ispartof><rights>2010 Karlsruhe Institute of Technology</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c377t-29afbe0e8ffef6ccbc20ff1d5cce9deeb6b0ca0c53753d9fb122a98eb10d55b83</citedby><cites>FETCH-LOGICAL-c377t-29afbe0e8ffef6ccbc20ff1d5cce9deeb6b0ca0c53753d9fb122a98eb10d55b83</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0920379610004898$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3536,23910,23911,25119,27903,27904,65309</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=24766267$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Fietz, W.H.</creatorcontrib><creatorcontrib>Heller, R.</creatorcontrib><creatorcontrib>Schlachter, S.I.</creatorcontrib><creatorcontrib>Goldacker, W.</creatorcontrib><title>Application of high temperature superconductors for fusion</title><title>Fusion engineering and design</title><description>The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70
kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2
kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads @ 20
kA and 6 leads @ 25.7
kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads.
With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65
K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20
kA at high fields well above 10
T. The high field rules BiSCCO superconductors out at temperatures above 50
K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for DEMO. KIT has already demonstrated a scalable concept using RE-123 HTS tapes that are assembled to Roebel type conductors. This concept can be expanded to form Rutherford cables as starting point for a development of a high current fusion cable. The status and prospect of using HTS conductors for fusion is discussed.</description><subject>Applied sciences</subject><subject>Cables</subject><subject>Coils</subject><subject>Conductors</subject><subject>Controled nuclear fusion plants</subject><subject>Current leads</subject><subject>DEMO</subject><subject>Design engineering</subject><subject>Economics</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fusion magnets</subject><subject>High current</subject><subject>High temperature superconductor</subject><subject>High temperature superconductors</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>ITER</subject><subject>Superconductors</subject><subject>W7-X</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2011</creationdate><recordtype>article</recordtype><recordid>eNqFkE9LxDAQxYMouK5-BnsRT61JapPG27L4Dxa86Dmk08lulm5Tk1bw25tll70KAzMMvzePeYTcMlowysTDtrBTxH7dYiw43W9ZQVl9RmaslmUumRLnZEYVp3kplbgkVzFuKWUy1Yw8LYahc2BG5_vM22zj1ptsxN2AwYxTwCxOaQTftxOMPsTM-pAlw4Rfkwtruog3xz4nXy_Pn8u3fPXx-r5crHIopRxzroxtkGJtLVoB0ACn1rK2AkDVIjaioWAoVKWsylbZhnFuVI0No21VNXU5J_eHu0Pw3xPGUe9cBOw606OfolairCuhFEukPJAQfIwBrR6C25nwqxnV-7D0Vp_C0vuwNGM6hZWUd0cPE8F0NpgeXDzJ-aMUgguZuMWBw_Twj8OgIzjsAVsXEEbdevev1x_VDIa9</recordid><startdate>20111001</startdate><enddate>20111001</enddate><creator>Fietz, W.H.</creator><creator>Heller, R.</creator><creator>Schlachter, S.I.</creator><creator>Goldacker, W.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20111001</creationdate><title>Application of high temperature superconductors for fusion</title><author>Fietz, W.H. ; Heller, R. ; Schlachter, S.I. ; Goldacker, W.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c377t-29afbe0e8ffef6ccbc20ff1d5cce9deeb6b0ca0c53753d9fb122a98eb10d55b83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2011</creationdate><topic>Applied sciences</topic><topic>Cables</topic><topic>Coils</topic><topic>Conductors</topic><topic>Controled nuclear fusion plants</topic><topic>Current leads</topic><topic>DEMO</topic><topic>Design engineering</topic><topic>Economics</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fusion magnets</topic><topic>High current</topic><topic>High temperature superconductor</topic><topic>High temperature superconductors</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>ITER</topic><topic>Superconductors</topic><topic>W7-X</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Fietz, W.H.</creatorcontrib><creatorcontrib>Heller, R.</creatorcontrib><creatorcontrib>Schlachter, S.I.</creatorcontrib><creatorcontrib>Goldacker, W.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Fietz, W.H.</au><au>Heller, R.</au><au>Schlachter, S.I.</au><au>Goldacker, W.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Application of high temperature superconductors for fusion</atitle><jtitle>Fusion engineering and design</jtitle><date>2011-10-01</date><risdate>2011</risdate><volume>86</volume><issue>6</issue><spage>1365</spage><epage>1368</epage><pages>1365-1368</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>The use of High Temperature Superconductor (HTS) materials in future fusion machines can increase the efficiency drastically. For ITER, W7-X and JT-60SA the economic benefit of HTS current leads was recognized after a 70
kA HTS current lead demonstrator was designed, fabricated and successfully tested by Karlsruhe Institute of Technology (KIT, which is a merge of former Forschungszentrum Karlsruhe and University of Karlsruhe). For ITER, the Chinese Domestic Agency will provide the current leads as a part of the superconducting feeder system. KIT is in charge of design, construction and test of HTS current leads for W7-X and JT-60SA. For W7-X 14 current leads with a maximum current of 18.2
kA are required that are oriented with the room temperature end at the bottom. JT60-SA will need 26 current leads (20 leads @ 20
kA and 6 leads @ 25.7
kA) which are mounted in vertical, normal position. These current leads are based on BiSCCO HTS superconductors, demonstrating that HTS material is now state of the art for highly efficient current leads.
With respect to future fusion reactors, it would be very promising to use HTS material not only in current leads but also in coils. This would allow a large increase of efficiency if the coils could be operated at temperatures ≥65
K. With such a high temperature it would be possible to omit the radiation shield of the coils, resulting in a less complex cryostat and a size reduction of the machine. In addition less refrigeration power is needed saving investment and operating costs. However, to come to an HTS fusion coil it is necessary to develop low ac loss HTS cables for currents well above 20
kA at high fields well above 10
T. The high field rules BiSCCO superconductors out at temperatures above 50
K, but RE-123 superconductors are promising. The development of a high current, high field RE-123 HTS fusion cable will not be targeted outside fusion community and has to be in the frame of a long term development programme for DEMO. KIT has already demonstrated a scalable concept using RE-123 HTS tapes that are assembled to Roebel type conductors. This concept can be expanded to form Rutherford cables as starting point for a development of a high current fusion cable. The status and prospect of using HTS conductors for fusion is discussed.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2010.11.018</doi><tpages>4</tpages></addata></record> |
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subjects | Applied sciences Cables Coils Conductors Controled nuclear fusion plants Current leads DEMO Design engineering Economics Energy Energy. Thermal use of fuels Exact sciences and technology Fusion magnets High current High temperature superconductor High temperature superconductors Installations for energy generation and conversion: thermal and electrical energy ITER Superconductors W7-X |
title | Application of high temperature superconductors for fusion |
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