Refurbishment of JET magnetic diagnostics
In a tokamak device, magnetic diagnostics play a key role in: (i) the understanding of plasma physics, (ii) control and (iii) safe operation (Ariola and Pironti [1]). JET plasmas have magnetic fluctuations from a large variety of MHD instabilities (Wesson, 2000) and is equipped with fast magnetic Mi...
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| Veröffentlicht in: | Fusion engineering and design 2019-09, Vol.146, p.2781-2785 |
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| container_title | Fusion engineering and design |
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| creator | Artaserse, G. Baruzzo, M. Henriques, R.B. Gerasimov, S. Lam, N. Tsalas, M. |
| description | In a tokamak device, magnetic diagnostics play a key role in: (i) the understanding of plasma physics, (ii) control and (iii) safe operation (Ariola and Pironti [1]). JET plasmas have magnetic fluctuations from a large variety of MHD instabilities (Wesson, 2000) and is equipped with fast magnetic Mirnov coils (Giovannozzi et al., 2014; Nave et al., 2004; Heeter et al., 2000) for spectral and mode number analysis. By the end of 2016 (end of experimental campaign C36B), JET had lost almost all pick-up coils used for MHD analysis (fast Mirnov coils). In order to restore the JET MHD modes analysis capability for the coming DT campaign, 25 + 2 faulty in-vessel coils were refurbished. A new coil design was implemented to try to diminish the failure rate, mitigating the possible cause that led to those failures. New sensors will use GLIDCOP® (Boyer et al., 2015) wire and will be remotely-handleable (RH) compatible. |
| doi_str_mv | 10.1016/j.fusengdes.2019.05.032 |
| format | Article |
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JET plasmas have magnetic fluctuations from a large variety of MHD instabilities (Wesson, 2000) and is equipped with fast magnetic Mirnov coils (Giovannozzi et al., 2014; Nave et al., 2004; Heeter et al., 2000) for spectral and mode number analysis. By the end of 2016 (end of experimental campaign C36B), JET had lost almost all pick-up coils used for MHD analysis (fast Mirnov coils). In order to restore the JET MHD modes analysis capability for the coming DT campaign, 25 + 2 faulty in-vessel coils were refurbished. A new coil design was implemented to try to diminish the failure rate, mitigating the possible cause that led to those failures. 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JET plasmas have magnetic fluctuations from a large variety of MHD instabilities (Wesson, 2000) and is equipped with fast magnetic Mirnov coils (Giovannozzi et al., 2014; Nave et al., 2004; Heeter et al., 2000) for spectral and mode number analysis. By the end of 2016 (end of experimental campaign C36B), JET had lost almost all pick-up coils used for MHD analysis (fast Mirnov coils). In order to restore the JET MHD modes analysis capability for the coming DT campaign, 25 + 2 faulty in-vessel coils were refurbished. A new coil design was implemented to try to diminish the failure rate, mitigating the possible cause that led to those failures. New sensors will use GLIDCOP® (Boyer et al., 2015) wire and will be remotely-handleable (RH) compatible.</description><subject>Calibration</subject><subject>Design of MHD coils</subject><subject>Failure rates</subject><subject>Joint European Torus</subject><subject>Magnetic variations</subject><subject>Mirnov coils</subject><subject>Pickup coils</subject><subject>Plasma physics</subject><subject>Plasmas</subject><subject>Refurbishment</subject><subject>Remote handling</subject><subject>Tokamak devices</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNqFkE9LxDAQxYMouK5-BguePLROkrZJjsuy_mNBkPUcssl0TbHtmrSC394sK16FgZnDe29mfoRcUygo0PquLZopYr9zGAsGVBVQFcDZCZlRKXguqKpPyQwUg5wLVZ-TixhbACpSzcjtKzZT2Pr43mE_ZkOTPa82WWd2PY7eZs6naYhpjJfkrDEfEa9--5y83a82y8d8_fLwtFysc8sljDk31lSslHRrBENbMsO4U5Q2Fp2rbQXScKas4I01DJFJdFDW0lRlLZSDms_JzTF3H4bPCeOo22EKfVqpGQfBpWCcJpU4qmwYYgzY6H3wnQnfmoI-cNGt_uOiD1w0VDpxSc7F0YnpiS-PQUfrsU_n-YB21G7w_2b8AFvjby8</recordid><startdate>20190901</startdate><enddate>20190901</enddate><creator>Artaserse, G.</creator><creator>Baruzzo, M.</creator><creator>Henriques, R.B.</creator><creator>Gerasimov, S.</creator><creator>Lam, N.</creator><creator>Tsalas, M.</creator><general>Elsevier B.V</general><general>Elsevier Science Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope><orcidid>https://orcid.org/0000-0002-9616-731X</orcidid></search><sort><creationdate>20190901</creationdate><title>Refurbishment of JET magnetic diagnostics</title><author>Artaserse, G. ; Baruzzo, M. ; Henriques, R.B. ; Gerasimov, S. ; Lam, N. ; Tsalas, M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c380t-3aca52481ba72ec42a23d911fcedd6c508a329c73fca2ee28ed0468a54679d063</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>Calibration</topic><topic>Design of MHD coils</topic><topic>Failure rates</topic><topic>Joint European Torus</topic><topic>Magnetic variations</topic><topic>Mirnov coils</topic><topic>Pickup coils</topic><topic>Plasma physics</topic><topic>Plasmas</topic><topic>Refurbishment</topic><topic>Remote handling</topic><topic>Tokamak devices</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Artaserse, G.</creatorcontrib><creatorcontrib>Baruzzo, M.</creatorcontrib><creatorcontrib>Henriques, R.B.</creatorcontrib><creatorcontrib>Gerasimov, S.</creatorcontrib><creatorcontrib>Lam, N.</creatorcontrib><creatorcontrib>Tsalas, M.</creatorcontrib><collection>CrossRef</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace 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>Artaserse, G.</au><au>Baruzzo, M.</au><au>Henriques, R.B.</au><au>Gerasimov, S.</au><au>Lam, N.</au><au>Tsalas, M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Refurbishment of JET magnetic diagnostics</atitle><jtitle>Fusion engineering and design</jtitle><date>2019-09-01</date><risdate>2019</risdate><volume>146</volume><spage>2781</spage><epage>2785</epage><pages>2781-2785</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>In a tokamak device, magnetic diagnostics play a key role in: (i) the understanding of plasma physics, (ii) control and (iii) safe operation (Ariola and Pironti [1]). JET plasmas have magnetic fluctuations from a large variety of MHD instabilities (Wesson, 2000) and is equipped with fast magnetic Mirnov coils (Giovannozzi et al., 2014; Nave et al., 2004; Heeter et al., 2000) for spectral and mode number analysis. By the end of 2016 (end of experimental campaign C36B), JET had lost almost all pick-up coils used for MHD analysis (fast Mirnov coils). In order to restore the JET MHD modes analysis capability for the coming DT campaign, 25 + 2 faulty in-vessel coils were refurbished. A new coil design was implemented to try to diminish the failure rate, mitigating the possible cause that led to those failures. New sensors will use GLIDCOP® (Boyer et al., 2015) wire and will be remotely-handleable (RH) compatible.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2019.05.032</doi><tpages>5</tpages><orcidid>https://orcid.org/0000-0002-9616-731X</orcidid></addata></record> |
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| source | Elsevier ScienceDirect Journals |
| subjects | Calibration Design of MHD coils Failure rates Joint European Torus Magnetic variations Mirnov coils Pickup coils Plasma physics Plasmas Refurbishment Remote handling Tokamak devices |
| title | Refurbishment of JET magnetic diagnostics |
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