Loading…
Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system
In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in t...
Saved in:
| Published in: | IEEE transactions on applied superconductivity 2005-06, Vol.15 (2), p.1496-1499 |
|---|---|
| Main Authors: | , , , , , , , , , , , , , , , , |
| Format: | Article |
| Language: | English |
| Subjects: | |
| Citations: | Items that this one cites Items that cite this one |
| Online Access: | Get full text |
| Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
| cited_by | cdi_FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263 |
|---|---|
| cites | cdi_FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263 |
| container_end_page | 1499 |
| container_issue | 2 |
| container_start_page | 1496 |
| container_title | IEEE transactions on applied superconductivity |
| container_volume | 15 |
| creator | Heller, R. Darweschsad, S.M. Dittrich, G. Fietz, W.H. Fink, S. Herz, W. Hurd, F. Kienzler, A. Lingor, A. Meyer, I. Nother, G. Susser, M. Tanna, V.L. Vostner, A. Wesche, R. Wuchner, F. Zahn, G. |
| description | In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed. |
| doi_str_mv | 10.1109/TASC.2005.849145 |
| format | article |
| fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_crossref_primary_10_1109_TASC_2005_849145</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><ieee_id>1439928</ieee_id><sourcerecordid>28125117</sourcerecordid><originalsourceid>FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263</originalsourceid><addsrcrecordid>eNp9kc1r3DAQxU1poGnSe6EXUWh78lajD3t0XJZtEwgU0u1ZyPI469QfW0mG5L-Plg0EcuhBaOD93oOZVxQfga8AuPm-W__erATneoXKgNJvinPQGkuhQb_NM9dQohDyXfE-xnvOQaHS50XaPhwo9CNNyQ0sUFyGFNncMcdqzv6u2b6_27NEY6ZcWgKxuOTRz1O7-DQH5pcQspkN5FrW0jhPMWUyK11-aU_sere9ZaO7myix-Bhz1mVx1rkh0ofn_6L482O721yVN79-Xm_WN6UXBlMpmwaU6FSlJDSq7qDtGu8dofMN1QKQao9ZqWStoOEkvW-9EZq71jglKnlRfDvlHsL8b6GY7NhHT8PgJpqXaNFUgLWUOpNf_0sKhHxIqDP4-RV4Py9hyltYA4KjQsQM8RPkwxxjoM4e8oldeLTA7bEte2zLHtuyp7ay5ctzroveDV1wk-_ji68yEisFmft04noiepGVNEagfALUjJ6O</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>912084888</pqid></control><display><type>article</type><title>Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system</title><source>IEEE Electronic Library (IEL) Journals</source><creator>Heller, R. ; Darweschsad, S.M. ; Dittrich, G. ; Fietz, W.H. ; Fink, S. ; Herz, W. ; Hurd, F. ; Kienzler, A. ; Lingor, A. ; Meyer, I. ; Nother, G. ; Susser, M. ; Tanna, V.L. ; Vostner, A. ; Wesche, R. ; Wuchner, F. ; Zahn, G.</creator><creatorcontrib>Heller, R. ; Darweschsad, S.M. ; Dittrich, G. ; Fietz, W.H. ; Fink, S. ; Herz, W. ; Hurd, F. ; Kienzler, A. ; Lingor, A. ; Meyer, I. ; Nother, G. ; Susser, M. ; Tanna, V.L. ; Vostner, A. ; Wesche, R. ; Wuchner, F. ; Zahn, G.</creatorcontrib><description>In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed.</description><identifier>ISSN: 1051-8223</identifier><identifier>EISSN: 1558-2515</identifier><identifier>DOI: 10.1109/TASC.2005.849145</identifier><identifier>CODEN: ITASE9</identifier><language>eng</language><publisher>New York, NY: IEEE</publisher><subject>Applied sciences ; Coils ; Contact ; Copper ; Current leads ; Electric connection. Cables. Wiring ; Electric contacts ; Electrical engineering. Electrical power engineering ; Electromagnets ; Exact sciences and technology ; fusion magnets ; high temperature superconductor ; High temperature superconductors ; Lead ; Mass flow rate ; Plasma temperature ; Safety ; Safety margins ; Steady state ; Superconducting coils ; Superconducting magnets ; Superconductivity ; Temperature distribution ; Testing ; Various equipment and components</subject><ispartof>IEEE transactions on applied superconductivity, 2005-06, Vol.15 (2), p.1496-1499</ispartof><rights>2005 INIST-CNRS</rights><rights>Copyright The Institute of Electrical and Electronics Engineers, Inc. (IEEE) 2005</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263</citedby><cites>FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://ieeexplore.ieee.org/document/1439928$$EHTML$$P50$$Gieee$$H</linktohtml><link.rule.ids>310,311,315,786,790,795,796,23958,23959,25170,27957,27958,55147</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=16938641$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Heller, R.</creatorcontrib><creatorcontrib>Darweschsad, S.M.</creatorcontrib><creatorcontrib>Dittrich, G.</creatorcontrib><creatorcontrib>Fietz, W.H.</creatorcontrib><creatorcontrib>Fink, S.</creatorcontrib><creatorcontrib>Herz, W.</creatorcontrib><creatorcontrib>Hurd, F.</creatorcontrib><creatorcontrib>Kienzler, A.</creatorcontrib><creatorcontrib>Lingor, A.</creatorcontrib><creatorcontrib>Meyer, I.</creatorcontrib><creatorcontrib>Nother, G.</creatorcontrib><creatorcontrib>Susser, M.</creatorcontrib><creatorcontrib>Tanna, V.L.</creatorcontrib><creatorcontrib>Vostner, A.</creatorcontrib><creatorcontrib>Wesche, R.</creatorcontrib><creatorcontrib>Wuchner, F.</creatorcontrib><creatorcontrib>Zahn, G.</creatorcontrib><title>Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system</title><title>IEEE transactions on applied superconductivity</title><addtitle>TASC</addtitle><description>In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed.</description><subject>Applied sciences</subject><subject>Coils</subject><subject>Contact</subject><subject>Copper</subject><subject>Current leads</subject><subject>Electric connection. Cables. Wiring</subject><subject>Electric contacts</subject><subject>Electrical engineering. Electrical power engineering</subject><subject>Electromagnets</subject><subject>Exact sciences and technology</subject><subject>fusion magnets</subject><subject>high temperature superconductor</subject><subject>High temperature superconductors</subject><subject>Lead</subject><subject>Mass flow rate</subject><subject>Plasma temperature</subject><subject>Safety</subject><subject>Safety margins</subject><subject>Steady state</subject><subject>Superconducting coils</subject><subject>Superconducting magnets</subject><subject>Superconductivity</subject><subject>Temperature distribution</subject><subject>Testing</subject><subject>Various equipment and components</subject><issn>1051-8223</issn><issn>1558-2515</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2005</creationdate><recordtype>article</recordtype><recordid>eNp9kc1r3DAQxU1poGnSe6EXUWh78lajD3t0XJZtEwgU0u1ZyPI469QfW0mG5L-Plg0EcuhBaOD93oOZVxQfga8AuPm-W__erATneoXKgNJvinPQGkuhQb_NM9dQohDyXfE-xnvOQaHS50XaPhwo9CNNyQ0sUFyGFNncMcdqzv6u2b6_27NEY6ZcWgKxuOTRz1O7-DQH5pcQspkN5FrW0jhPMWUyK11-aU_sere9ZaO7myix-Bhz1mVx1rkh0ofn_6L482O721yVN79-Xm_WN6UXBlMpmwaU6FSlJDSq7qDtGu8dofMN1QKQao9ZqWStoOEkvW-9EZq71jglKnlRfDvlHsL8b6GY7NhHT8PgJpqXaNFUgLWUOpNf_0sKhHxIqDP4-RV4Py9hyltYA4KjQsQM8RPkwxxjoM4e8oldeLTA7bEte2zLHtuyp7ay5ctzroveDV1wk-_ji68yEisFmft04noiepGVNEagfALUjJ6O</recordid><startdate>200506</startdate><enddate>200506</enddate><creator>Heller, R.</creator><creator>Darweschsad, S.M.</creator><creator>Dittrich, G.</creator><creator>Fietz, W.H.</creator><creator>Fink, S.</creator><creator>Herz, W.</creator><creator>Hurd, F.</creator><creator>Kienzler, A.</creator><creator>Lingor, A.</creator><creator>Meyer, I.</creator><creator>Nother, G.</creator><creator>Susser, M.</creator><creator>Tanna, V.L.</creator><creator>Vostner, A.</creator><creator>Wesche, R.</creator><creator>Wuchner, F.</creator><creator>Zahn, G.</creator><general>IEEE</general><general>Institute of Electrical and Electronics Engineers</general><general>The Institute of Electrical and Electronics Engineers, Inc. (IEEE)</general><scope>97E</scope><scope>RIA</scope><scope>RIE</scope><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7U5</scope><scope>8FD</scope><scope>L7M</scope><scope>F28</scope><scope>FR3</scope></search><sort><creationdate>200506</creationdate><title>Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system</title><author>Heller, R. ; Darweschsad, S.M. ; Dittrich, G. ; Fietz, W.H. ; Fink, S. ; Herz, W. ; Hurd, F. ; Kienzler, A. ; Lingor, A. ; Meyer, I. ; Nother, G. ; Susser, M. ; Tanna, V.L. ; Vostner, A. ; Wesche, R. ; Wuchner, F. ; Zahn, G.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2005</creationdate><topic>Applied sciences</topic><topic>Coils</topic><topic>Contact</topic><topic>Copper</topic><topic>Current leads</topic><topic>Electric connection. Cables. Wiring</topic><topic>Electric contacts</topic><topic>Electrical engineering. Electrical power engineering</topic><topic>Electromagnets</topic><topic>Exact sciences and technology</topic><topic>fusion magnets</topic><topic>high temperature superconductor</topic><topic>High temperature superconductors</topic><topic>Lead</topic><topic>Mass flow rate</topic><topic>Plasma temperature</topic><topic>Safety</topic><topic>Safety margins</topic><topic>Steady state</topic><topic>Superconducting coils</topic><topic>Superconducting magnets</topic><topic>Superconductivity</topic><topic>Temperature distribution</topic><topic>Testing</topic><topic>Various equipment and components</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Heller, R.</creatorcontrib><creatorcontrib>Darweschsad, S.M.</creatorcontrib><creatorcontrib>Dittrich, G.</creatorcontrib><creatorcontrib>Fietz, W.H.</creatorcontrib><creatorcontrib>Fink, S.</creatorcontrib><creatorcontrib>Herz, W.</creatorcontrib><creatorcontrib>Hurd, F.</creatorcontrib><creatorcontrib>Kienzler, A.</creatorcontrib><creatorcontrib>Lingor, A.</creatorcontrib><creatorcontrib>Meyer, I.</creatorcontrib><creatorcontrib>Nother, G.</creatorcontrib><creatorcontrib>Susser, M.</creatorcontrib><creatorcontrib>Tanna, V.L.</creatorcontrib><creatorcontrib>Vostner, A.</creatorcontrib><creatorcontrib>Wesche, R.</creatorcontrib><creatorcontrib>Wuchner, F.</creatorcontrib><creatorcontrib>Zahn, G.</creatorcontrib><collection>IEEE All-Society Periodicals Package (ASPP) 2005-present</collection><collection>IEEE All-Society Periodicals Package (ASPP) 1998–Present</collection><collection>IEEE Xplore</collection><collection>Pascal-Francis</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>ANTE: Abstracts in New Technology & Engineering</collection><collection>Engineering Research Database</collection><jtitle>IEEE transactions on applied superconductivity</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Heller, R.</au><au>Darweschsad, S.M.</au><au>Dittrich, G.</au><au>Fietz, W.H.</au><au>Fink, S.</au><au>Herz, W.</au><au>Hurd, F.</au><au>Kienzler, A.</au><au>Lingor, A.</au><au>Meyer, I.</au><au>Nother, G.</au><au>Susser, M.</au><au>Tanna, V.L.</au><au>Vostner, A.</au><au>Wesche, R.</au><au>Wuchner, F.</au><au>Zahn, G.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system</atitle><jtitle>IEEE transactions on applied superconductivity</jtitle><stitle>TASC</stitle><date>2005-06</date><risdate>2005</risdate><volume>15</volume><issue>2</issue><spage>1496</spage><epage>1499</epage><pages>1496-1499</pages><issn>1051-8223</issn><eissn>1558-2515</eissn><coden>ITASE9</coden><notes>ObjectType-Article-2</notes><notes>SourceType-Scholarly Journals-1</notes><notes>ObjectType-Feature-1</notes><notes>content type line 23</notes><abstract>In the frame of the European Fusion Technology Programme, the Forschungszentrum Karlsruhe and the CRPP Villigen have designed and built a 70 kA current lead for the ITER TF Coils using High Temperature Superconductors (HTS). At the beginning of 2004 the HTS current lead was installed and tested in the TOSKA facility of the Forschungszentrum Karlsruhe. The scope of the experiment was to characterize the current lead in steady state conditions and to explore the operation limits as well. For this, the temperature profile, the contact resistances, the heat load at 4.5 K, the required 50 K He mass flow rate, and the temperature margin were evaluated. The safety margin in case of a loss of He mass flow was studied, too. The paper describes the experimental results as well as the thermal and electrical models developed.</abstract><cop>New York, NY</cop><pub>IEEE</pub><doi>10.1109/TASC.2005.849145</doi><tpages>4</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 1051-8223 |
| ispartof | IEEE transactions on applied superconductivity, 2005-06, Vol.15 (2), p.1496-1499 |
| issn | 1051-8223 1558-2515 |
| language | eng |
| recordid | cdi_crossref_primary_10_1109_TASC_2005_849145 |
| source | IEEE Electronic Library (IEL) Journals |
| subjects | Applied sciences Coils Contact Copper Current leads Electric connection. Cables. Wiring Electric contacts Electrical engineering. Electrical power engineering Electromagnets Exact sciences and technology fusion magnets high temperature superconductor High temperature superconductors Lead Mass flow rate Plasma temperature Safety Safety margins Steady state Superconducting coils Superconducting magnets Superconductivity Temperature distribution Testing Various equipment and components |
| title | Experimental results of a 70 kA high temperature superconductor current lead demonstrator for the ITER magnet system |
| url | http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2024-09-22T04%3A34%3A48IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Experimental%20results%20of%20a%2070%20kA%20high%20temperature%20superconductor%20current%20lead%20demonstrator%20for%20the%20ITER%20magnet%20system&rft.jtitle=IEEE%20transactions%20on%20applied%20superconductivity&rft.au=Heller,%20R.&rft.date=2005-06&rft.volume=15&rft.issue=2&rft.spage=1496&rft.epage=1499&rft.pages=1496-1499&rft.issn=1051-8223&rft.eissn=1558-2515&rft.coden=ITASE9&rft_id=info:doi/10.1109/TASC.2005.849145&rft_dat=%3Cproquest_cross%3E28125117%3C/proquest_cross%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-c298t-3bb142f46431b47f1dfbccae8acbe7218e7c81b463741b0e3ccdc9250ad9a4263%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_pqid=912084888&rft_id=info:pmid/&rft_ieee_id=1439928&rfr_iscdi=true |