Current status of tokamak T-15MD
•T-15MD project is aimed at obtaining a database for creating a thermonuclear neutron source for atomic energy needs.•Magnet system of T-15MD will confine the hot plasma in the divertor configuration.•Toroidal magnetic field at the plasma axis is 2 T, plasma current is 2 MA.•Preparation to physical...
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creator | Khvostenko, P.P. Anashkin, I.O. Bondarchuk, E.N. Chudnovsky, A.N. Kavin, A.A. Khvostenko, A.P. Kirneva, N.A. Kuzmin, E.G. Levin, I.V. Leonov, V.M. Lutchenko, A.V. Modyaev, A.L. Nikolaev, A.V. Notkin, G.E. Romannikov, A.N. Roy, I.N. Sokolov, M.M. Sushkov, A.V. |
description | •T-15MD project is aimed at obtaining a database for creating a thermonuclear neutron source for atomic energy needs.•Magnet system of T-15MD will confine the hot plasma in the divertor configuration.•Toroidal magnetic field at the plasma axis is 2 T, plasma current is 2 MA.•Preparation to physical start-up of tokamak T-15MD is completed.•T-15MD should begin operation in 2021.
At the present time, the preparation to physical start-up of tokamak T-15MD is completed in the National Research Center “Kurchatov Institute”. The main parameters of T-15MD are: R = 1.48 m, a = 0.67 m, B = 2.0 T, Ipl = 2.0 MA. The magnet system is capable to maintain without overheating (more 60 °C) the plasma current of 2 MA for 4 s, 1 MA for 20 s, 700 kA for 40 s, 500 kA for 80 s, 300 kA for 160 s and 250 kA for 400 s. Plasma current drive can be maintained either by injection of fast neutrals or by electron cyclotron (EC)-, ion cyclotron (IC)- and low hybrid (LH) - waves. In August 2019 the electromagnetic system, consisting of TF and PF coils, together with vacuum vessel have been assembled in experimental hall. Power supply system of Tokamak T-15MD includes: two substations 110/10 kV, two substations 10/0.83 kV, thyristor convertors and different equipment. Total power consumption during the pulse with plasma current 2 MA and additional plasma heating of 20 MW will consist of 300 MVA. Power supply system is in the commissioning. Tokamak T-15MD will be operate using the information and control system. All the information and control system equipment, required for the implementation of physical start-up of tokamak T-15MD, is available. For plasma control the 250 different electromagnetic probes are installed inside vacuum vessel. The gyrotron with frequency 82.6 GHz and power of 1 MW will be used for pre-ionization. |
doi_str_mv | 10.1016/j.fusengdes.2020.112211 |
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At the present time, the preparation to physical start-up of tokamak T-15MD is completed in the National Research Center “Kurchatov Institute”. The main parameters of T-15MD are: R = 1.48 m, a = 0.67 m, B = 2.0 T, Ipl = 2.0 MA. The magnet system is capable to maintain without overheating (more 60 °C) the plasma current of 2 MA for 4 s, 1 MA for 20 s, 700 kA for 40 s, 500 kA for 80 s, 300 kA for 160 s and 250 kA for 400 s. Plasma current drive can be maintained either by injection of fast neutrals or by electron cyclotron (EC)-, ion cyclotron (IC)- and low hybrid (LH) - waves. In August 2019 the electromagnetic system, consisting of TF and PF coils, together with vacuum vessel have been assembled in experimental hall. Power supply system of Tokamak T-15MD includes: two substations 110/10 kV, two substations 10/0.83 kV, thyristor convertors and different equipment. Total power consumption during the pulse with plasma current 2 MA and additional plasma heating of 20 MW will consist of 300 MVA. Power supply system is in the commissioning. Tokamak T-15MD will be operate using the information and control system. All the information and control system equipment, required for the implementation of physical start-up of tokamak T-15MD, is available. For plasma control the 250 different electromagnetic probes are installed inside vacuum vessel. The gyrotron with frequency 82.6 GHz and power of 1 MW will be used for pre-ionization.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2020.112211</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Coils ; Control equipment ; Control systems ; Cyclotrons ; Magnet system ; Overheating ; Physical start-up ; Plasma ; Plasma control ; Plasma currents ; Plasma heating ; Power consumption ; Power supply ; Power supply system ; Preionization ; Research facilities ; Substations ; Thyristors ; Tokamak ; Tokamak devices ; Vessels</subject><ispartof>Fusion engineering and design, 2021-03, Vol.164, p.112211, Article 112211</ispartof><rights>2021 Elsevier B.V.</rights><rights>Copyright Elsevier Science Ltd. Mar 2021</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c343t-75efb73efe54d4bf5caaac454be0d6fc77d5633222de70eafa857bfc7d5ec6013</citedby><cites>FETCH-LOGICAL-c343t-75efb73efe54d4bf5caaac454be0d6fc77d5633222de70eafa857bfc7d5ec6013</cites><orcidid>0000-0001-9458-2184</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2020.112211$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,777,781,3537,27905,27906,45976</link.rule.ids></links><search><creatorcontrib>Khvostenko, P.P.</creatorcontrib><creatorcontrib>Anashkin, I.O.</creatorcontrib><creatorcontrib>Bondarchuk, E.N.</creatorcontrib><creatorcontrib>Chudnovsky, A.N.</creatorcontrib><creatorcontrib>Kavin, A.A.</creatorcontrib><creatorcontrib>Khvostenko, A.P.</creatorcontrib><creatorcontrib>Kirneva, N.A.</creatorcontrib><creatorcontrib>Kuzmin, E.G.</creatorcontrib><creatorcontrib>Levin, I.V.</creatorcontrib><creatorcontrib>Leonov, V.M.</creatorcontrib><creatorcontrib>Lutchenko, A.V.</creatorcontrib><creatorcontrib>Modyaev, A.L.</creatorcontrib><creatorcontrib>Nikolaev, A.V.</creatorcontrib><creatorcontrib>Notkin, G.E.</creatorcontrib><creatorcontrib>Romannikov, A.N.</creatorcontrib><creatorcontrib>Roy, I.N.</creatorcontrib><creatorcontrib>Sokolov, M.M.</creatorcontrib><creatorcontrib>Sushkov, A.V.</creatorcontrib><title>Current status of tokamak T-15MD</title><title>Fusion engineering and design</title><description>•T-15MD project is aimed at obtaining a database for creating a thermonuclear neutron source for atomic energy needs.•Magnet system of T-15MD will confine the hot plasma in the divertor configuration.•Toroidal magnetic field at the plasma axis is 2 T, plasma current is 2 MA.•Preparation to physical start-up of tokamak T-15MD is completed.•T-15MD should begin operation in 2021.
At the present time, the preparation to physical start-up of tokamak T-15MD is completed in the National Research Center “Kurchatov Institute”. The main parameters of T-15MD are: R = 1.48 m, a = 0.67 m, B = 2.0 T, Ipl = 2.0 MA. The magnet system is capable to maintain without overheating (more 60 °C) the plasma current of 2 MA for 4 s, 1 MA for 20 s, 700 kA for 40 s, 500 kA for 80 s, 300 kA for 160 s and 250 kA for 400 s. Plasma current drive can be maintained either by injection of fast neutrals or by electron cyclotron (EC)-, ion cyclotron (IC)- and low hybrid (LH) - waves. In August 2019 the electromagnetic system, consisting of TF and PF coils, together with vacuum vessel have been assembled in experimental hall. Power supply system of Tokamak T-15MD includes: two substations 110/10 kV, two substations 10/0.83 kV, thyristor convertors and different equipment. Total power consumption during the pulse with plasma current 2 MA and additional plasma heating of 20 MW will consist of 300 MVA. Power supply system is in the commissioning. Tokamak T-15MD will be operate using the information and control system. All the information and control system equipment, required for the implementation of physical start-up of tokamak T-15MD, is available. For plasma control the 250 different electromagnetic probes are installed inside vacuum vessel. The gyrotron with frequency 82.6 GHz and power of 1 MW will be used for pre-ionization.</description><subject>Coils</subject><subject>Control equipment</subject><subject>Control systems</subject><subject>Cyclotrons</subject><subject>Magnet system</subject><subject>Overheating</subject><subject>Physical start-up</subject><subject>Plasma</subject><subject>Plasma control</subject><subject>Plasma currents</subject><subject>Plasma heating</subject><subject>Power consumption</subject><subject>Power supply</subject><subject>Power supply system</subject><subject>Preionization</subject><subject>Research facilities</subject><subject>Substations</subject><subject>Thyristors</subject><subject>Tokamak</subject><subject>Tokamak devices</subject><subject>Vessels</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2021</creationdate><recordtype>article</recordtype><recordid>eNqFkE9LAzEQxYMoWKufwQXPWzPJJukeS_0LFS_1HLLJRHZrd2uSFfz2pqx4FQYGHu-9YX6EXANdAAV52y38GLF_dxgXjLKsAmMAJ2QGS8VLBbU8JTNaM1pyVctzchFjRymoPDNSrMcQsE9FTCaNsRh8kYad2ZtdsS1BvNxdkjNvPiJe_e45eXu4366fys3r4_N6tSktr3gqlUDfKI4eReWqxgtrjLGVqBqkTnqrlBOSc8aYQ0XReLMUqsm6E2glBT4nN1PvIQyfI8aku2EMfT6pmQAqaQVKZpeaXDYMMQb0-hDavQnfGqg-4tCd_sOhjzj0hCMnV1MS8xNfLQYdbYu9RdcGtEm7of234wesYGua</recordid><startdate>202103</startdate><enddate>202103</enddate><creator>Khvostenko, P.P.</creator><creator>Anashkin, I.O.</creator><creator>Bondarchuk, E.N.</creator><creator>Chudnovsky, A.N.</creator><creator>Kavin, A.A.</creator><creator>Khvostenko, A.P.</creator><creator>Kirneva, N.A.</creator><creator>Kuzmin, E.G.</creator><creator>Levin, I.V.</creator><creator>Leonov, V.M.</creator><creator>Lutchenko, A.V.</creator><creator>Modyaev, A.L.</creator><creator>Nikolaev, A.V.</creator><creator>Notkin, G.E.</creator><creator>Romannikov, A.N.</creator><creator>Roy, I.N.</creator><creator>Sokolov, M.M.</creator><creator>Sushkov, A.V.</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/0000-0001-9458-2184</orcidid></search><sort><creationdate>202103</creationdate><title>Current status of tokamak T-15MD</title><author>Khvostenko, P.P. ; Anashkin, I.O. ; Bondarchuk, E.N. ; Chudnovsky, A.N. ; Kavin, A.A. ; Khvostenko, A.P. ; Kirneva, N.A. ; Kuzmin, E.G. ; Levin, I.V. ; Leonov, V.M. ; Lutchenko, A.V. ; Modyaev, A.L. ; Nikolaev, A.V. ; Notkin, G.E. ; Romannikov, A.N. ; Roy, I.N. ; Sokolov, M.M. ; Sushkov, A.V.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c343t-75efb73efe54d4bf5caaac454be0d6fc77d5633222de70eafa857bfc7d5ec6013</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2021</creationdate><topic>Coils</topic><topic>Control equipment</topic><topic>Control systems</topic><topic>Cyclotrons</topic><topic>Magnet system</topic><topic>Overheating</topic><topic>Physical start-up</topic><topic>Plasma</topic><topic>Plasma control</topic><topic>Plasma currents</topic><topic>Plasma heating</topic><topic>Power consumption</topic><topic>Power supply</topic><topic>Power supply system</topic><topic>Preionization</topic><topic>Research facilities</topic><topic>Substations</topic><topic>Thyristors</topic><topic>Tokamak</topic><topic>Tokamak devices</topic><topic>Vessels</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Khvostenko, P.P.</creatorcontrib><creatorcontrib>Anashkin, I.O.</creatorcontrib><creatorcontrib>Bondarchuk, E.N.</creatorcontrib><creatorcontrib>Chudnovsky, A.N.</creatorcontrib><creatorcontrib>Kavin, A.A.</creatorcontrib><creatorcontrib>Khvostenko, A.P.</creatorcontrib><creatorcontrib>Kirneva, N.A.</creatorcontrib><creatorcontrib>Kuzmin, E.G.</creatorcontrib><creatorcontrib>Levin, I.V.</creatorcontrib><creatorcontrib>Leonov, V.M.</creatorcontrib><creatorcontrib>Lutchenko, A.V.</creatorcontrib><creatorcontrib>Modyaev, A.L.</creatorcontrib><creatorcontrib>Nikolaev, A.V.</creatorcontrib><creatorcontrib>Notkin, G.E.</creatorcontrib><creatorcontrib>Romannikov, A.N.</creatorcontrib><creatorcontrib>Roy, I.N.</creatorcontrib><creatorcontrib>Sokolov, M.M.</creatorcontrib><creatorcontrib>Sushkov, A.V.</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>Khvostenko, P.P.</au><au>Anashkin, I.O.</au><au>Bondarchuk, E.N.</au><au>Chudnovsky, A.N.</au><au>Kavin, A.A.</au><au>Khvostenko, A.P.</au><au>Kirneva, N.A.</au><au>Kuzmin, E.G.</au><au>Levin, I.V.</au><au>Leonov, V.M.</au><au>Lutchenko, A.V.</au><au>Modyaev, A.L.</au><au>Nikolaev, A.V.</au><au>Notkin, G.E.</au><au>Romannikov, A.N.</au><au>Roy, I.N.</au><au>Sokolov, M.M.</au><au>Sushkov, A.V.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Current status of tokamak T-15MD</atitle><jtitle>Fusion engineering and design</jtitle><date>2021-03</date><risdate>2021</risdate><volume>164</volume><spage>112211</spage><pages>112211-</pages><artnum>112211</artnum><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>•T-15MD project is aimed at obtaining a database for creating a thermonuclear neutron source for atomic energy needs.•Magnet system of T-15MD will confine the hot plasma in the divertor configuration.•Toroidal magnetic field at the plasma axis is 2 T, plasma current is 2 MA.•Preparation to physical start-up of tokamak T-15MD is completed.•T-15MD should begin operation in 2021.
At the present time, the preparation to physical start-up of tokamak T-15MD is completed in the National Research Center “Kurchatov Institute”. The main parameters of T-15MD are: R = 1.48 m, a = 0.67 m, B = 2.0 T, Ipl = 2.0 MA. The magnet system is capable to maintain without overheating (more 60 °C) the plasma current of 2 MA for 4 s, 1 MA for 20 s, 700 kA for 40 s, 500 kA for 80 s, 300 kA for 160 s and 250 kA for 400 s. Plasma current drive can be maintained either by injection of fast neutrals or by electron cyclotron (EC)-, ion cyclotron (IC)- and low hybrid (LH) - waves. In August 2019 the electromagnetic system, consisting of TF and PF coils, together with vacuum vessel have been assembled in experimental hall. Power supply system of Tokamak T-15MD includes: two substations 110/10 kV, two substations 10/0.83 kV, thyristor convertors and different equipment. Total power consumption during the pulse with plasma current 2 MA and additional plasma heating of 20 MW will consist of 300 MVA. Power supply system is in the commissioning. Tokamak T-15MD will be operate using the information and control system. All the information and control system equipment, required for the implementation of physical start-up of tokamak T-15MD, is available. For plasma control the 250 different electromagnetic probes are installed inside vacuum vessel. The gyrotron with frequency 82.6 GHz and power of 1 MW will be used for pre-ionization.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2020.112211</doi><orcidid>https://orcid.org/0000-0001-9458-2184</orcidid></addata></record> |
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subjects | Coils Control equipment Control systems Cyclotrons Magnet system Overheating Physical start-up Plasma Plasma control Plasma currents Plasma heating Power consumption Power supply Power supply system Preionization Research facilities Substations Thyristors Tokamak Tokamak devices Vessels |
title | Current status of tokamak T-15MD |
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