Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin
In the International Thermonuclear Experimental Reactor, the nuclear radiation escaping from the vacuum vessel reaches the superconducting toroidal field (TF) magnets, affecting the temperature margin ΔT mar , that is, the difference between the current sharing temperature and the operating temperat...
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Veröffentlicht in: | IEEE transactions on applied superconductivity 2014-06, Vol.24 (3), p.1-4 |
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creator | Savoldi Richard, Laura Bonifetto, Roberto Bottero, Umberto Foussat, Arnaud Mitchell, Neil Seo, Kazutaka Zanino, Roberto |
description | In the International Thermonuclear Experimental Reactor, the nuclear radiation escaping from the vacuum vessel reaches the superconducting toroidal field (TF) magnets, affecting the temperature margin ΔT mar , that is, the difference between the current sharing temperature and the operating temperature. The TF magnets are designed to operate at a minimum margin ΔT mar min = 0.7 K. Recent design activity on in-vessel components, for example, blanket, in-vessel coils for plasma stability, suggests a potential enhancement of the nuclear heat load, leading to a reduction of ΔT mar , which is accurately assessed in the paper using the validated 4C code. For the case when the margin goes below the minimum, different possible mitigation strategies are investigated: the first considers the possible reduction of the He bath temperature from the nominal 4.3 K down to 3.8 K, and is proven to be successful. The others consider the possible increase of the dwell time between plasma pulses, and is shown to be inadequate, or the decrease of plasma pulse duration, which turns out to be effective below 300 s. |
doi_str_mv | 10.1109/TASC.2013.2280720 |
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The TF magnets are designed to operate at a minimum margin ΔT mar min = 0.7 K. Recent design activity on in-vessel components, for example, blanket, in-vessel coils for plasma stability, suggests a potential enhancement of the nuclear heat load, leading to a reduction of ΔT mar , which is accurately assessed in the paper using the validated 4C code. For the case when the margin goes below the minimum, different possible mitigation strategies are investigated: the first considers the possible reduction of the He bath temperature from the nominal 4.3 K down to 3.8 K, and is proven to be successful. The others consider the possible increase of the dwell time between plasma pulses, and is shown to be inadequate, or the decrease of plasma pulse duration, which turns out to be effective below 300 s.</description><identifier>ISSN: 1051-8223</identifier><identifier>EISSN: 1558-2515</identifier><identifier>DOI: 10.1109/TASC.2013.2280720</identifier><identifier>CODEN: ITASE9</identifier><language>eng</language><publisher>New York, NY: IEEE</publisher><subject>Applied sciences ; Coils ; Cooling ; Electrical engineering. 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The TF magnets are designed to operate at a minimum margin ΔT mar min = 0.7 K. Recent design activity on in-vessel components, for example, blanket, in-vessel coils for plasma stability, suggests a potential enhancement of the nuclear heat load, leading to a reduction of ΔT mar , which is accurately assessed in the paper using the validated 4C code. For the case when the margin goes below the minimum, different possible mitigation strategies are investigated: the first considers the possible reduction of the He bath temperature from the nominal 4.3 K down to 3.8 K, and is proven to be successful. The others consider the possible increase of the dwell time between plasma pulses, and is shown to be inadequate, or the decrease of plasma pulse duration, which turns out to be effective below 300 s.</description><subject>Applied sciences</subject><subject>Coils</subject><subject>Cooling</subject><subject>Electrical engineering. Electrical power engineering</subject><subject>Electromagnets</subject><subject>Exact sciences and technology</subject><subject>Heating</subject><subject>International thermonuclear experimental reactor (ITER)</subject><subject>nuclear fusion</subject><subject>Plasma temperature</subject><subject>simulation</subject><subject>Superconducting magnets</subject><subject>Various equipment and components</subject><subject>Windings</subject><issn>1051-8223</issn><issn>1558-2515</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2014</creationdate><recordtype>article</recordtype><sourceid>RIE</sourceid><recordid>eNo9kD1PwzAQhi0EEqXwAxCLF8aUs91LnLGqCq1UQIJMLNGRnEtQmlR2OvTfk9Cq0328H8MjxL2CiVKQPmWzz_lEgzITrS0kGi7ESCHaSKPCy34HVJHV2lyLmxB-AdTUTnEkvmYN1YdQBdk62f2wXDjHRXc-3_ZFzeTlkqmT65ZK2Tb_wipbfMjsWb7SpuHen_F2x566vef-5zdVcyuuHNWB705zLLLnRTZfRuv3l9V8to4KnWIXld9UaITCkkKDJrGpg6kxVDIikaLYxRjHTjtwpixd4hATxchAxoCzZizUsbbwbQieXb7z1Zb8IVeQD2zygU0-sMlPbPrM4zGzo1BQ7Tw1RRXOQW1jaw0Mvoejr2LmsxyjTRUq8wdZSmv1</recordid><startdate>20140601</startdate><enddate>20140601</enddate><creator>Savoldi Richard, Laura</creator><creator>Bonifetto, Roberto</creator><creator>Bottero, Umberto</creator><creator>Foussat, Arnaud</creator><creator>Mitchell, Neil</creator><creator>Seo, Kazutaka</creator><creator>Zanino, Roberto</creator><general>IEEE</general><general>Institute of Electrical and Electronics Engineers</general><scope>97E</scope><scope>RIA</scope><scope>RIE</scope><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20140601</creationdate><title>Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin</title><author>Savoldi Richard, Laura ; Bonifetto, Roberto ; Bottero, Umberto ; Foussat, Arnaud ; Mitchell, Neil ; Seo, Kazutaka ; Zanino, Roberto</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c295t-dbac250c8a15353789f0433ade55aa1a6f6566f2f0f3ddf7f5571e5e0a330f83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2014</creationdate><topic>Applied sciences</topic><topic>Coils</topic><topic>Cooling</topic><topic>Electrical engineering. Electrical power engineering</topic><topic>Electromagnets</topic><topic>Exact sciences and technology</topic><topic>Heating</topic><topic>International thermonuclear experimental reactor (ITER)</topic><topic>nuclear fusion</topic><topic>Plasma temperature</topic><topic>simulation</topic><topic>Superconducting magnets</topic><topic>Various equipment and components</topic><topic>Windings</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Savoldi Richard, Laura</creatorcontrib><creatorcontrib>Bonifetto, Roberto</creatorcontrib><creatorcontrib>Bottero, Umberto</creatorcontrib><creatorcontrib>Foussat, Arnaud</creatorcontrib><creatorcontrib>Mitchell, Neil</creatorcontrib><creatorcontrib>Seo, Kazutaka</creatorcontrib><creatorcontrib>Zanino, Roberto</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>Pascal-Francis</collection><collection>CrossRef</collection><jtitle>IEEE transactions on applied superconductivity</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>Savoldi Richard, Laura</au><au>Bonifetto, Roberto</au><au>Bottero, Umberto</au><au>Foussat, Arnaud</au><au>Mitchell, Neil</au><au>Seo, Kazutaka</au><au>Zanino, Roberto</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin</atitle><jtitle>IEEE transactions on applied superconductivity</jtitle><stitle>TASC</stitle><date>2014-06-01</date><risdate>2014</risdate><volume>24</volume><issue>3</issue><spage>1</spage><epage>4</epage><pages>1-4</pages><issn>1051-8223</issn><eissn>1558-2515</eissn><coden>ITASE9</coden><abstract>In the International Thermonuclear Experimental Reactor, the nuclear radiation escaping from the vacuum vessel reaches the superconducting toroidal field (TF) magnets, affecting the temperature margin ΔT mar , that is, the difference between the current sharing temperature and the operating temperature. The TF magnets are designed to operate at a minimum margin ΔT mar min = 0.7 K. Recent design activity on in-vessel components, for example, blanket, in-vessel coils for plasma stability, suggests a potential enhancement of the nuclear heat load, leading to a reduction of ΔT mar , which is accurately assessed in the paper using the validated 4C code. For the case when the margin goes below the minimum, different possible mitigation strategies are investigated: the first considers the possible reduction of the He bath temperature from the nominal 4.3 K down to 3.8 K, and is proven to be successful. The others consider the possible increase of the dwell time between plasma pulses, and is shown to be inadequate, or the decrease of plasma pulse duration, which turns out to be effective below 300 s.</abstract><cop>New York, NY</cop><pub>IEEE</pub><doi>10.1109/TASC.2013.2280720</doi><tpages>4</tpages></addata></record> |
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subjects | Applied sciences Coils Cooling Electrical engineering. Electrical power engineering Electromagnets Exact sciences and technology Heating International thermonuclear experimental reactor (ITER) nuclear fusion Plasma temperature simulation Superconducting magnets Various equipment and components Windings |
title | Analysis of the Effects of the Nuclear Heat Load on the ITER TF Magnets Temperature Margin |
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