New Version of the KTM Lithium Divertor
At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithiu...
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| Veröffentlicht in: | Physics of atomic nuclei 2020-12, Vol.83 (7), p.1116-1123 |
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| container_title | Physics of atomic nuclei |
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| creator | Vertkov, A. V. Zharkov, M. Yu Lyublinski, I. E. Berlov, A. V. Tazhibayeva, I. L. Ponkratov, Yu. V. Gordienko, Yu. N. |
| description | At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithium capillary porous systems has been developed and tested successfully in real tokamak conditions. In this design, the problem of removing high-density heat flows is solved by using liquid metal coolant based on the Na–K eutectic alloy. The requirements for the improved safety and the divertor design compatibility with other in-vessel water-cooled elements of the tokamak and temperature limitation of the receiving lithium surface to the level |
| doi_str_mv | 10.1134/S1063778820070121 |
| format | Article |
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2
stipulated a new design solution of the divertor experimental module and the use of a totally new coolant—water flow dispersed with gas (gas-water spray). In the paper, the design solutions of the new version of the module, the coolant parameters, and the cooling system layout are described and substantiated. The experimental results on determining the heat transfer coefficient of the coolant based on gas-water spray are considered.</description><identifier>ISSN: 1063-7788</identifier><identifier>EISSN: 1562-692X</identifier><identifier>DOI: 10.1134/S1063778820070121</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Alloys ; Coolants ; Cooling systems ; Design optimization ; Eutectic alloys ; Heat transfer coefficients ; Heat transmission ; Liquid metals ; Lithium ; Modules ; Nuclear energy ; Particle and Nuclear Physics ; Physics ; Physics and Astronomy ; Product enhancement ; Tokamak devices ; Tokamaks ; Water flow ; Water sprays</subject><ispartof>Physics of atomic nuclei, 2020-12, Vol.83 (7), p.1116-1123</ispartof><rights>Pleiades Publishing, Ltd. 2020. ISSN 1063-7788, Physics of Atomic Nuclei, 2020, Vol. 83, No. 7, pp. 1116–1123. © Pleiades Publishing, Ltd., 2020. Russian Text © The Author(s), 2019, published in Voprosy Atomnoi Nauki i Tekhniki, Seriya: Termoyadernyi Sintez, 2019, Vol. 42, No. 4, pp. 5–13.</rights><rights>COPYRIGHT 2020 Springer</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c389t-db6f0272b1c82464edefda6087f3cc51dff1e17bbacb78c164269190cc04921e3</citedby><cites>FETCH-LOGICAL-c389t-db6f0272b1c82464edefda6087f3cc51dff1e17bbacb78c164269190cc04921e3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.1134/S1063778820070121$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.1134/S1063778820070121$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,780,784,27924,27925,41488,42557,51319</link.rule.ids></links><search><creatorcontrib>Vertkov, A. V.</creatorcontrib><creatorcontrib>Zharkov, M. Yu</creatorcontrib><creatorcontrib>Lyublinski, I. E.</creatorcontrib><creatorcontrib>Berlov, A. V.</creatorcontrib><creatorcontrib>Tazhibayeva, I. L.</creatorcontrib><creatorcontrib>Ponkratov, Yu. V.</creatorcontrib><creatorcontrib>Gordienko, Yu. N.</creatorcontrib><title>New Version of the KTM Lithium Divertor</title><title>Physics of atomic nuclei</title><addtitle>Phys. Atom. Nuclei</addtitle><description>At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithium capillary porous systems has been developed and tested successfully in real tokamak conditions. In this design, the problem of removing high-density heat flows is solved by using liquid metal coolant based on the Na–K eutectic alloy. The requirements for the improved safety and the divertor design compatibility with other in-vessel water-cooled elements of the tokamak and temperature limitation of the receiving lithium surface to the level <600°C at the heat flows of 10–20 MW/m
2
stipulated a new design solution of the divertor experimental module and the use of a totally new coolant—water flow dispersed with gas (gas-water spray). In the paper, the design solutions of the new version of the module, the coolant parameters, and the cooling system layout are described and substantiated. The experimental results on determining the heat transfer coefficient of the coolant based on gas-water spray are considered.</description><subject>Alloys</subject><subject>Coolants</subject><subject>Cooling systems</subject><subject>Design optimization</subject><subject>Eutectic alloys</subject><subject>Heat transfer coefficients</subject><subject>Heat transmission</subject><subject>Liquid metals</subject><subject>Lithium</subject><subject>Modules</subject><subject>Nuclear energy</subject><subject>Particle and Nuclear Physics</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Product enhancement</subject><subject>Tokamak devices</subject><subject>Tokamaks</subject><subject>Water flow</subject><subject>Water sprays</subject><issn>1063-7788</issn><issn>1562-692X</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2020</creationdate><recordtype>article</recordtype><recordid>eNp1kN1LwzAQwIMoOKd_gG8FH8SHzlzapunjmF_DqeCm-BbaNNkytmYmqR__vRkVRETuIUfu97tLDqFjwAOAJD2fAqZJnjNGMM4xENhBPcgoiWlBXnZDHsrxtr6PDpxbYgzAMtxDp_fyPXqW1mnTREZFfiGj29ldNNF-odt1dKHfpPXGHqI9Va6cPPo---jp6nI2uoknD9fj0XASi4QVPq4rqjDJSQWCkZSmspaqLilmuUqEyKBWCiTkVVWKKmcCaEpoAQUWAqcFAZn00UnXd2PNayud50vT2iaM5CRlLPyGJmmgBh01L1eS60YZb0sRopZrLUwjlQ73Q5pBVlCCt8LZLyEwXn74edk6x8fTx98sdKywxjkrFd9YvS7tJwfMt8vmf5YdHNI5LrDNXNqfZ_8vfQGrd30j</recordid><startdate>20201201</startdate><enddate>20201201</enddate><creator>Vertkov, A. V.</creator><creator>Zharkov, M. Yu</creator><creator>Lyublinski, I. E.</creator><creator>Berlov, A. V.</creator><creator>Tazhibayeva, I. L.</creator><creator>Ponkratov, Yu. V.</creator><creator>Gordienko, Yu. N.</creator><general>Pleiades Publishing</general><general>Springer</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope><scope>ISR</scope></search><sort><creationdate>20201201</creationdate><title>New Version of the KTM Lithium Divertor</title><author>Vertkov, A. V. ; Zharkov, M. Yu ; Lyublinski, I. E. ; Berlov, A. V. ; Tazhibayeva, I. L. ; Ponkratov, Yu. V. ; Gordienko, Yu. 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Yu</creatorcontrib><creatorcontrib>Lyublinski, I. E.</creatorcontrib><creatorcontrib>Berlov, A. V.</creatorcontrib><creatorcontrib>Tazhibayeva, I. L.</creatorcontrib><creatorcontrib>Ponkratov, Yu. V.</creatorcontrib><creatorcontrib>Gordienko, Yu. N.</creatorcontrib><collection>CrossRef</collection><collection>Gale In Context: Science</collection><jtitle>Physics of atomic nuclei</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Vertkov, A. V.</au><au>Zharkov, M. Yu</au><au>Lyublinski, I. E.</au><au>Berlov, A. V.</au><au>Tazhibayeva, I. L.</au><au>Ponkratov, Yu. V.</au><au>Gordienko, Yu. N.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>New Version of the KTM Lithium Divertor</atitle><jtitle>Physics of atomic nuclei</jtitle><stitle>Phys. Atom. Nuclei</stitle><date>2020-12-01</date><risdate>2020</risdate><volume>83</volume><issue>7</issue><spage>1116</spage><epage>1123</epage><pages>1116-1123</pages><issn>1063-7788</issn><eissn>1562-692X</eissn><abstract>At present, the Kazakhstan Tokamak for Material testing (KTM) project is in progress. The optimization of innovative design elements of the divertor is carried out at the KTM, in addition to studying materials applied for fusion technologies. The design of the lithium divertor module based on lithium capillary porous systems has been developed and tested successfully in real tokamak conditions. In this design, the problem of removing high-density heat flows is solved by using liquid metal coolant based on the Na–K eutectic alloy. The requirements for the improved safety and the divertor design compatibility with other in-vessel water-cooled elements of the tokamak and temperature limitation of the receiving lithium surface to the level <600°C at the heat flows of 10–20 MW/m
2
stipulated a new design solution of the divertor experimental module and the use of a totally new coolant—water flow dispersed with gas (gas-water spray). In the paper, the design solutions of the new version of the module, the coolant parameters, and the cooling system layout are described and substantiated. The experimental results on determining the heat transfer coefficient of the coolant based on gas-water spray are considered.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.1134/S1063778820070121</doi><tpages>8</tpages></addata></record> |
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| subjects | Alloys Coolants Cooling systems Design optimization Eutectic alloys Heat transfer coefficients Heat transmission Liquid metals Lithium Modules Nuclear energy Particle and Nuclear Physics Physics Physics and Astronomy Product enhancement Tokamak devices Tokamaks Water flow Water sprays |
| title | New Version of the KTM Lithium Divertor |
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