Analysis and design of the beryllium tiles for the JET ITER-like wall project
Work is in progress to completely replace, in 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent with the ITER design. The ITER-like wall (ILW) will be created with a combination of beryllium (Be), tungsten (W), W-coated CFC and Be-coated inconel tiles, wit...
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| Veröffentlicht in: | Fusion engineering and design 2007-10, Vol.82 (15), p.1706-1712 |
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| container_title | Fusion engineering and design |
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| creator | Thompson, V. Krivchenkov, Y. Riccardo, V. Vizvary, Z. |
| description | Work is in progress to completely replace, in 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent with the ITER design. The ITER-like wall (ILW) will be created with a combination of beryllium (Be), tungsten (W), W-coated CFC and Be-coated inconel tiles, with the material depending on the local anticipated heat flux and geometry. Over 4000 tiles will be replaced and the ILW will accommodate additional heating up to at least 50
MW for 10
s. One of the objectives is to maintain or improve the existing CFC tile power handling performance which has been achieved in most cases by hiding bolt holes, optimising tile size and profile and introducing castellations on plasma facing surfaces. This paper describes the generic problems associated with the Be tiles (power handling capacity and disruption induced eddy currents) and illustrates the solution selected for the inner wall guard limiter (IWGL) where the present CFC tiles will be replaced with Be. |
| doi_str_mv | 10.1016/j.fusengdes.2007.05.022 |
| format | Article |
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MW for 10
s. One of the objectives is to maintain or improve the existing CFC tile power handling performance which has been achieved in most cases by hiding bolt holes, optimising tile size and profile and introducing castellations on plasma facing surfaces. This paper describes the generic problems associated with the Be tiles (power handling capacity and disruption induced eddy currents) and illustrates the solution selected for the inner wall guard limiter (IWGL) where the present CFC tiles will be replaced with Be.</description><subject>Applied sciences</subject><subject>Beryllium</subject><subject>Castellations</subject><subject>Controled nuclear fusion plants</subject><subject>Eddy currents</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>First wall tiles</subject><subject>Hot spot melting</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>JET</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2007</creationdate><recordtype>article</recordtype><recordid>eNqFkEtLAzEQx4MoWB-fwVz0tmuy6eZxLFJfVASp55BNJjU13dVkq_Tbu7WiR2FgYPg_mB9CZ5SUlFB-uSz9OkO7cJDLihBRkrokVbWHRlQKVgiq-D4aEVWRggnFD9FRzktCqBhmhB4mrYmbHDI2rcNDRli0uPO4fwHcQNrEGNYr3IcIGfsufd_vp3N8N58-FTG8Av40MeK31C3B9ifowJuY4fRnH6Pn6-n86raYPd7cXU1mhWWC90UNQjbQABdSVkZ670wtJGfjRoGvwY25c4pZqZzzrDKikSCMM7xWNauk8uwYXexyh973NeRer0K2EKNpoVtnzYjiQtDxIBQ7oU1dzgm8fkthZdJGU6K3-PRS_-LTW3ya1HrANzjPfypMtib6ZFob8p9dMVEJutVNdjoY_v0IkHS2AVoLLqSBiHZd-LfrCzVrinY</recordid><startdate>20071001</startdate><enddate>20071001</enddate><creator>Thompson, V.</creator><creator>Krivchenkov, Y.</creator><creator>Riccardo, V.</creator><creator>Vizvary, Z.</creator><general>Elsevier B.V</general><general>Elsevier Science</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SP</scope><scope>7TB</scope><scope>7U5</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20071001</creationdate><title>Analysis and design of the beryllium tiles for the JET ITER-like wall project</title><author>Thompson, V. ; Krivchenkov, Y. ; Riccardo, V. ; Vizvary, Z.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c376t-5e78bebe67882a8ffda578634b9ef5ed46dd93c89ddf32a7b8e7ada65953289f3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2007</creationdate><topic>Applied sciences</topic><topic>Beryllium</topic><topic>Castellations</topic><topic>Controled nuclear fusion plants</topic><topic>Eddy currents</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>First wall tiles</topic><topic>Hot spot melting</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>JET</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Thompson, V.</creatorcontrib><creatorcontrib>Krivchenkov, Y.</creatorcontrib><creatorcontrib>Riccardo, V.</creatorcontrib><creatorcontrib>Vizvary, Z.</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>Thompson, V.</au><au>Krivchenkov, Y.</au><au>Riccardo, V.</au><au>Vizvary, Z.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Analysis and design of the beryllium tiles for the JET ITER-like wall project</atitle><jtitle>Fusion engineering and design</jtitle><date>2007-10-01</date><risdate>2007</risdate><volume>82</volume><issue>15</issue><spage>1706</spage><epage>1712</epage><pages>1706-1712</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><coden>FEDEEE</coden><abstract>Work is in progress to completely replace, in 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent with the ITER design. The ITER-like wall (ILW) will be created with a combination of beryllium (Be), tungsten (W), W-coated CFC and Be-coated inconel tiles, with the material depending on the local anticipated heat flux and geometry. Over 4000 tiles will be replaced and the ILW will accommodate additional heating up to at least 50
MW for 10
s. One of the objectives is to maintain or improve the existing CFC tile power handling performance which has been achieved in most cases by hiding bolt holes, optimising tile size and profile and introducing castellations on plasma facing surfaces. This paper describes the generic problems associated with the Be tiles (power handling capacity and disruption induced eddy currents) and illustrates the solution selected for the inner wall guard limiter (IWGL) where the present CFC tiles will be replaced with Be.</abstract><cop>Amsterdam</cop><cop>New York, NY</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2007.05.022</doi><tpages>7</tpages></addata></record> |
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| ispartof | Fusion engineering and design, 2007-10, Vol.82 (15), p.1706-1712 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals Complete |
| subjects | Applied sciences Beryllium Castellations Controled nuclear fusion plants Eddy currents Energy Energy. Thermal use of fuels Exact sciences and technology First wall tiles Hot spot melting Installations for energy generation and conversion: thermal and electrical energy JET |
| title | Analysis and design of the beryllium tiles for the JET ITER-like wall project |
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