Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak
The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000 s and may be severed as a valuable pre-testing...
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| Veröffentlicht in: | Fusion engineering and design 2007-10, Vol.82 (15), p.2347-2352 |
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| creator | Liu, Songlin Bai, Yunqing Zheng, Shanliang Chen, Hongli Wang, Weihua Long, Pengcheng Wu, Yican |
| description | The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000
s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses. |
| doi_str_mv | 10.1016/j.fusengdes.2007.07.041 |
| format | Article |
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s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2007.07.041</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Breeding blanket ; Controled nuclear fusion plants ; EAST device ; EAST-TBM ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Installations for energy generation and conversion: thermal and electrical energy ; ITER</subject><ispartof>Fusion engineering and design, 2007-10, Vol.82 (15), p.2347-2352</ispartof><rights>2007 Elsevier B.V.</rights><rights>2008 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c376t-f360dabcc9ef422dbe894d0a575dccc045aa11c26d88a538da3fc2751dbf9d2c3</citedby><cites>FETCH-LOGICAL-c376t-f360dabcc9ef422dbe894d0a575dccc045aa11c26d88a538da3fc2751dbf9d2c3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.fusengdes.2007.07.041$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,780,784,789,790,3550,23930,23931,25140,27924,27925,45995</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=19372806$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Liu, Songlin</creatorcontrib><creatorcontrib>Bai, Yunqing</creatorcontrib><creatorcontrib>Zheng, Shanliang</creatorcontrib><creatorcontrib>Chen, Hongli</creatorcontrib><creatorcontrib>Wang, Weihua</creatorcontrib><creatorcontrib>Long, Pengcheng</creatorcontrib><creatorcontrib>Wu, Yican</creatorcontrib><creatorcontrib>FDS Team</creatorcontrib><title>Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak</title><title>Fusion engineering and design</title><description>The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000
s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses.</description><subject>Applied sciences</subject><subject>Breeding blanket</subject><subject>Controled nuclear fusion plants</subject><subject>EAST device</subject><subject>EAST-TBM</subject><subject>Energy</subject><subject>Energy. 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Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>ITER</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Liu, Songlin</creatorcontrib><creatorcontrib>Bai, Yunqing</creatorcontrib><creatorcontrib>Zheng, Shanliang</creatorcontrib><creatorcontrib>Chen, Hongli</creatorcontrib><creatorcontrib>Wang, Weihua</creatorcontrib><creatorcontrib>Long, Pengcheng</creatorcontrib><creatorcontrib>Wu, Yican</creatorcontrib><creatorcontrib>FDS Team</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research 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>Liu, Songlin</au><au>Bai, Yunqing</au><au>Zheng, Shanliang</au><au>Chen, Hongli</au><au>Wang, Weihua</au><au>Long, Pengcheng</au><au>Wu, Yican</au><aucorp>FDS Team</aucorp><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak</atitle><jtitle>Fusion engineering and design</jtitle><date>2007-10-01</date><risdate>2007</risdate><volume>82</volume><issue>15</issue><spage>2347</spage><epage>2352</epage><pages>2347-2352</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>The Chinese Experimental Advanced Superconducting Tokamak (EAST) has been successfully constructed and has produced a discharge of plasma in ×2006. It aims to achieve static-state operation of high performance D-D plasma with a long pulse of up to 1000
s and may be severed as a valuable pre-testing platform for Test Blanket Module (TBM) prior to International Thermonuclear Experimental Reactor (ITER). Based on the Chinese Dual Function Lithium Lead TBM (DFLL-TBM) design and its testing plan for ITER and EAST, a lithium lead test blanket module concept for the EAST (EAST-TBM) has been proposed as an important R&D activity and is expected to be tested in EAST focusing on electro-magnetics and thermo-mechanics performances of the TBM, including the influence of TBM made of ferromagnetic steel on tokamak plasma. This paper presents the status of EAST-TBM design, including design guideline, main features, instrumentation configuration, and installation in EAST port. The feasibility of the EAST-TBM has been validated with the preliminary performance analyses.</abstract><cop>Amsterdam</cop><cop>New York, NY</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2007.07.041</doi><tpages>6</tpages></addata></record> |
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| ispartof | Fusion engineering and design, 2007-10, Vol.82 (15), p.2347-2352 |
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| language | eng |
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| source | ScienceDirect Journals (5 years ago - present) |
| subjects | Applied sciences Breeding blanket Controled nuclear fusion plants EAST device EAST-TBM Energy Energy. Thermal use of fuels Exact sciences and technology Installations for energy generation and conversion: thermal and electrical energy ITER |
| title | Preliminary design of lithium lead test blanket module for the Chinese Experimental Advanced Superconducting Tokamak |
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