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Material migration and fuel retention studies during the JET carbon divertor campaigns
http://hdl.handle.net/10655/00013051
http://hdl.handle.net/10655/000130516d15c66b-5b4d-4507-ae64-92688e6e96f1
Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2022-02-17 | |||||
タイトル | ||||||
タイトル | Material migration and fuel retention studies during the JET carbon divertor campaigns | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Fusion | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | JET | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Divertor | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Carbon | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Plasma-facing components | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
資源タイプ | journal article | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
Coad, J.P.
× Coad, J.P.× RUBEL, M.× LIKONEN, J.× Bekris, N.× Brezinsek, S.× Matthews, G.F.× Mayer, M.× Widdowson, A.M.× JET Contributors, |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The first divertor was installed in the JET machine between 1992 and 1994 and was operated with carbon tiles and then beryllium tiles in 1994–5. Post-mortem studies after these first experiments demonstrated that most of the impurities deposited in the divertor originate in the main chamber, and that asymmetric deposition patterns generally favouring the inner divertor region result from drift in the scrape-off layer. A new monolithic divertor structure was installed in 1996 which produced heavy deposition at shadowed areas in the inner divertor corner, which is where the majority of the tritium was trapped by co-deposition during the deuterium-tritium experiment in 1997. Different divertor geometries have been tested since such as the Gas-Box and High-Delta divertors; a principle objective has been to predict plasma behaviour, transport and tritium retention in ITER. Transport modelling experiments were carried out at the end of four campaigns by puffing 13C-labelled methane, and a range of diagnostics such as quartz-microbalance and rotating collectors have been installed to add time resolution to the post-mortem analyses. The study of material migration after D-D and D-T campaigns clearly revealed important consequences of fuel retention in the presence of carbon walls. They gave a strong impulse to make a fundamental change of wall materials. In 2010 the carbon divertor and wall tiles were removed and replaced with tiles with Be or W surfaces for the ITER-Like Wall Project. | |||||
書誌情報 |
Fusion Engineering and Design 巻 138, p. 78-108, 発行日 2019-01 |
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出版者 | ||||||
出版者 | ELSEVIER | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 09203796 | |||||
書誌レコードID | ||||||
収録物識別子タイプ | NCID | |||||
収録物識別子 | AA10691446 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2018.10.002 | |||||
権利 | ||||||
権利情報 | © 2019. This manuscript version is made available under the CC-BY-NC-ND 4.0 license https://creativecommons.org/licenses/by-nc-nd/4.0/ | |||||
情報源 | ||||||
関連名称 | J.P. Coad, M. Rubel, J. Likonen, N. Bekris, S. Brezinsek, G.F. Matthews, M. Mayer, A.M. Widdowson, Material migration and fuel retention studies during the JET carbon divertor campaigns, Fusion Engineering and Design, Volume 138, 2019, Pages 78-108, ISSN 0920-3796, https://doi.org/10.1016/j.fusengdes.2018.10.002. | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.fusengdes.2018.10.002 | |||||
関連名称 | Publisher version | |||||
NAIS | ||||||
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