Preparation of interfaces in ITER for integrating the Test Blanket Systems
Up to six mock-ups of different tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. The paper describes the recent studies performed by the IO for the preparation of the most urgent interfaces required for the integration of...
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| Veröffentlicht in: | Fusion engineering and design 2010-12, Vol.85 (10), p.1829-1833 |
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| creator | Giancarli, L. Bede, O. Beloglazov, S. Benchikhoune, M. Chang, K.P. Chuyanov, V. Dell’Orco, G. Friconneau, J.P. Gicquel, S. Gliss, C. Hansalia, C. Iseli, M. Kim, C.S. Kuehn, I. Levesy, B. Maluta, F.T. Merola, M. Pascal, R. Patisson, L. Rigoni, G. Snipes, J. Tesini, A. Yonekawa, I. |
| description | Up to six mock-ups of different tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. The paper describes the recent studies performed by the IO for the preparation of the most urgent interfaces required for the integration of the TBSs into the ITER device and Tokamak complex.
Main addressed items concern the impact of the TBM ferromagnetic structural material on plasma performance, the preliminary design of the TBM frame, the main dimensions and location for the TBM cooling systems and for the Tritium circuits, and preliminary requirement for measurement systems.
A large effort has also been devoted to the proposed maintenance/refurbishment procedure and to the space and equipment requirements in the hot cell facility, including provisions for the shipping of TBM sub-components outside the ITER site for post-irradiation examinations. |
| doi_str_mv | 10.1016/j.fusengdes.2010.06.005 |
| format | Article |
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Main addressed items concern the impact of the TBM ferromagnetic structural material on plasma performance, the preliminary design of the TBM frame, the main dimensions and location for the TBM cooling systems and for the Tritium circuits, and preliminary requirement for measurement systems.
A large effort has also been devoted to the proposed maintenance/refurbishment procedure and to the space and equipment requirements in the hot cell facility, including provisions for the shipping of TBM sub-components outside the ITER site for post-irradiation examinations.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2010.06.005</identifier><identifier>CODEN: FEDEEE</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Blanketing ; Breeding blankets ; Circuits ; Controled nuclear fusion plants ; Design engineering ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Ferromagnetic materials ; Installations for energy generation and conversion: thermal and electrical energy ; Interfaces ; Maintenance ; Preliminary designs ; Refurbishment ; TBM ; Tokamak devices ; Tritium ; Tritium production</subject><ispartof>Fusion engineering and design, 2010-12, Vol.85 (10), p.1829-1833</ispartof><rights>2010</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c377t-f12dba3c615fcf129e1a4b6434c62628d0e827381e6935aa04d49f6c930b5ce43</citedby><cites>FETCH-LOGICAL-c377t-f12dba3c615fcf129e1a4b6434c62628d0e827381e6935aa04d49f6c930b5ce43</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://www.sciencedirect.com/science/article/pii/S0920379610002619$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>309,310,314,776,780,785,786,3537,23909,23910,25118,27901,27902,65306</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=23734251$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Giancarli, L.</creatorcontrib><creatorcontrib>Bede, O.</creatorcontrib><creatorcontrib>Beloglazov, S.</creatorcontrib><creatorcontrib>Benchikhoune, M.</creatorcontrib><creatorcontrib>Chang, K.P.</creatorcontrib><creatorcontrib>Chuyanov, V.</creatorcontrib><creatorcontrib>Dell’Orco, G.</creatorcontrib><creatorcontrib>Friconneau, J.P.</creatorcontrib><creatorcontrib>Gicquel, S.</creatorcontrib><creatorcontrib>Gliss, C.</creatorcontrib><creatorcontrib>Hansalia, C.</creatorcontrib><creatorcontrib>Iseli, M.</creatorcontrib><creatorcontrib>Kim, C.S.</creatorcontrib><creatorcontrib>Kuehn, I.</creatorcontrib><creatorcontrib>Levesy, B.</creatorcontrib><creatorcontrib>Maluta, F.T.</creatorcontrib><creatorcontrib>Merola, M.</creatorcontrib><creatorcontrib>Pascal, R.</creatorcontrib><creatorcontrib>Patisson, L.</creatorcontrib><creatorcontrib>Rigoni, G.</creatorcontrib><creatorcontrib>Snipes, J.</creatorcontrib><creatorcontrib>Tesini, A.</creatorcontrib><creatorcontrib>Yonekawa, I.</creatorcontrib><title>Preparation of interfaces in ITER for integrating the Test Blanket Systems</title><title>Fusion engineering and design</title><description>Up to six mock-ups of different tritium breeding blanket systems, referred to as Test Blanket Systems (TBS), will be tested in three equatorial ports of ITER. The paper describes the recent studies performed by the IO for the preparation of the most urgent interfaces required for the integration of the TBSs into the ITER device and Tokamak complex.
Main addressed items concern the impact of the TBM ferromagnetic structural material on plasma performance, the preliminary design of the TBM frame, the main dimensions and location for the TBM cooling systems and for the Tritium circuits, and preliminary requirement for measurement systems.
A large effort has also been devoted to the proposed maintenance/refurbishment procedure and to the space and equipment requirements in the hot cell facility, including provisions for the shipping of TBM sub-components outside the ITER site for post-irradiation examinations.</description><subject>Applied sciences</subject><subject>Blanketing</subject><subject>Breeding blankets</subject><subject>Circuits</subject><subject>Controled nuclear fusion plants</subject><subject>Design engineering</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Ferromagnetic materials</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Interfaces</subject><subject>Maintenance</subject><subject>Preliminary designs</subject><subject>Refurbishment</subject><subject>TBM</subject><subject>Tokamak devices</subject><subject>Tritium</subject><subject>Tritium production</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><recordid>eNqFkMtOAjEUhhujiYg-g7MxrmbsZaadLpGgYkg0iuumdE6xCDPYFhPe3iKErclJziXfuf0IXRNcEEz43aKwmwDtvIFQUJyqmBcYVyeoR2rBckEkP0U9LCnOmZD8HF2EsMCYiGQ99PzqYa29jq5rs85mro3grTYQUpiNp6O3zHb-rzzfUe08i5-QTSHE7H6p2y-I2fs2RFiFS3Rm9TLA1cH30cfDaDp8yicvj-PhYJIbJkTMLaHNTDPDSWVNSiQQXc54yUrDKad1g6GmgtUEuGSV1rhsSmm5kQzPKgMl66Pb_dy177436RC1csHAMl0D3SaomkshBWM4kWJPGt-F4MGqtXcr7beKYLUTTy3UUTy1E09hrpJ4qfPmsEMHo5fW69a4cGynTLCSViRxgz0H6eEfB14F46A10DgPJqqmc__u-gW0GIke</recordid><startdate>20101201</startdate><enddate>20101201</enddate><creator>Giancarli, L.</creator><creator>Bede, O.</creator><creator>Beloglazov, S.</creator><creator>Benchikhoune, M.</creator><creator>Chang, K.P.</creator><creator>Chuyanov, V.</creator><creator>Dell’Orco, G.</creator><creator>Friconneau, J.P.</creator><creator>Gicquel, S.</creator><creator>Gliss, C.</creator><creator>Hansalia, C.</creator><creator>Iseli, M.</creator><creator>Kim, C.S.</creator><creator>Kuehn, I.</creator><creator>Levesy, B.</creator><creator>Maluta, F.T.</creator><creator>Merola, M.</creator><creator>Pascal, R.</creator><creator>Patisson, L.</creator><creator>Rigoni, G.</creator><creator>Snipes, J.</creator><creator>Tesini, A.</creator><creator>Yonekawa, I.</creator><general>Elsevier B.V</general><general>Elsevier</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>20101201</creationdate><title>Preparation of interfaces in ITER for integrating the Test Blanket Systems</title><author>Giancarli, L. ; Bede, O. ; Beloglazov, S. ; Benchikhoune, M. ; Chang, K.P. ; Chuyanov, V. ; Dell’Orco, G. ; Friconneau, J.P. ; Gicquel, S. ; Gliss, C. ; Hansalia, C. ; Iseli, M. ; Kim, C.S. ; Kuehn, I. ; Levesy, B. ; Maluta, F.T. ; Merola, M. ; Pascal, R. ; Patisson, L. ; Rigoni, G. ; Snipes, J. ; Tesini, A. ; Yonekawa, I.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c377t-f12dba3c615fcf129e1a4b6434c62628d0e827381e6935aa04d49f6c930b5ce43</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><topic>Applied sciences</topic><topic>Blanketing</topic><topic>Breeding blankets</topic><topic>Circuits</topic><topic>Controled nuclear fusion plants</topic><topic>Design engineering</topic><topic>Energy</topic><topic>Energy. 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The paper describes the recent studies performed by the IO for the preparation of the most urgent interfaces required for the integration of the TBSs into the ITER device and Tokamak complex.
Main addressed items concern the impact of the TBM ferromagnetic structural material on plasma performance, the preliminary design of the TBM frame, the main dimensions and location for the TBM cooling systems and for the Tritium circuits, and preliminary requirement for measurement systems.
A large effort has also been devoted to the proposed maintenance/refurbishment procedure and to the space and equipment requirements in the hot cell facility, including provisions for the shipping of TBM sub-components outside the ITER site for post-irradiation examinations.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.fusengdes.2010.06.005</doi><tpages>5</tpages></addata></record> |
| fulltext | fulltext |
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| ispartof | Fusion engineering and design, 2010-12, Vol.85 (10), p.1829-1833 |
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| source | Elsevier ScienceDirect Journals |
| subjects | Applied sciences Blanketing Breeding blankets Circuits Controled nuclear fusion plants Design engineering Energy Energy. Thermal use of fuels Exact sciences and technology Ferromagnetic materials Installations for energy generation and conversion: thermal and electrical energy Interfaces Maintenance Preliminary designs Refurbishment TBM Tokamak devices Tritium Tritium production |
| title | Preparation of interfaces in ITER for integrating the Test Blanket Systems |
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