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Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device
http://hdl.handle.net/10655/00013481
http://hdl.handle.net/10655/0001348156cd3cf8-f434-403e-b1e9-0a756424a59d
名前 / ファイル | ライセンス | アクション |
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13332_.Nucl.Mat.Eng (4.5 MB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2022-09-27 | |||||
タイトル | ||||||
タイトル | Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | ERO2.0 | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Tungsten migration | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Plasma-wall interaction | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | EMC3-EIRENE | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | LHD | |||||
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 | |||||
著者 |
SHOJI, Mamoru
× SHOJI, Mamoru× KAWAMURA, Gakushi× ROMAZANOV, Juri× KIRSCHNER, Andreas× MASUZAKI, Suguru× TOKITANI, Masayuki× BREZINSEK, Sebastijan |
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著者ID | ||||||
内容記述タイプ | Other | |||||
内容記述 | 0000-0003-0655-7347 | |||||
抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0. The ERO2.0 simulation reproduced the measurement of localized tungsten migration from a tungsten-coated divertor plate installed in the inboard side of the torus. The simulation also explained the measurement of the high tungsten areal density in the private side on a carbon divertor plate, next to the tungsten-coated divertor plate, by the tungsten prompt redeposition in plasma discharges for a low magnetic field strength in a counterclockwise toroidal direction. However, the simulation disagreed with the measurement of low tungsten areal density on the plasma-wetted areas on the carbon divertor plates, which indicated that the actual erosion rate of the redeposited tungsten should be much higher than that used in the ERO2.0 code. | |||||
書誌情報 |
Nuclear Materials and Energy 巻 33, 号 October 2022, p. 101257, 発行日 2022-09 |
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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 | 2352-1791 | |||||
DOI | ||||||
関連タイプ | isIdenticalTo | |||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.nme.2022.101257 | |||||
権利 | ||||||
権利情報 | © 2022 The Author(s). Published by Elsevier Ltd. | |||||
権利 | ||||||
権利情報 | This article is available under the Creative Commons CC-BY-NC-ND license and permits non-commercial use of the work as published, without adaptation or alteration provided the work is fully attributed. | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.nme.2022.101257 | |||||
関連名称 | Publisher version | |||||
著者版フラグ | ||||||
出版タイプ | VoR | |||||
出版タイプResource | http://purl.org/coar/version/c_970fb48d4fbd8a85 | |||||
NAIS | ||||||
13332 |