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Novel divertor design to mitigate neutron irradiation in the helical reactor FFHR-d1
http://hdl.handle.net/10655/00012716
http://hdl.handle.net/10655/000127165fd1d9c4-280e-44d4-9d8b-fa42f6267904
名前 / ファイル | ライセンス | アクション |
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Fus.Eng.Des_98-99_pp1629-1633 (2.2 MB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2021-12-15 | |||||
タイトル | ||||||
タイトル | Novel divertor design to mitigate neutron irradiation in the helical reactor FFHR-d1 | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Helical reactor | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | FFHR | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Divertor | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Irradiation | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Superconducting magnet | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | Structural analys | |||||
キーワード | ||||||
主題Scheme | Other | |||||
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 |
TAMURA, Hitoshi
× TAMURA, Hitoshi× TANAKA, Teruya× GOTO, Takuya× MIYAZAWA, Junichi× MASUZAKI, Suguru× WATANABE, Tsuguhiro× YANAGI, Nagato× SAGARA, Akio× ITO, Satoshi× HASHIZUME1, Hidetoshi |
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著者ID | ||||||
内容記述タイプ | Other | |||||
内容記述 | 0000-0003-4210-9859 | |||||
抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The heat flux at the divertor in a fusion reactor is considered to have a peak of >10 MW/m2. In a design study of the helical reactor FFHR-d1, the feasibility of employing a copper alloy for divertor cooling pipes was investigated; however, radiation in the divertor area would quickly damage the copper alloy. The neutron load on the divertor can be reduced by a blanket arrangement; nevertheless, in the present divertor structure, irradiation damage of materials on the inboard side of the torus remains relatively high. If the divertor could be moved to an area receiving much less radiation, then the lifetimes of divertor materials should increase. In this paper, a novel divertor structure is introduced in which the coil-support structure is modified to create a region receiving relatively low amounts of radiation without changing the geometry of the helical or vertical field coils. Using this proposed design would increase the lifetime of the copper alloy in divertor components to more than an estimated six years. In addition, the divertor could be accessed from either the upper or lower sides of the device, simplifying maintenance. | |||||
書誌情報 |
Fusion Engineering and Design 巻 98-99, p. 1629-1633, 発行日 2015-02 |
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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 | 0920-3796 | |||||
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 | ||||||
関連タイプ | isVersionOf | |||||
識別子タイプ | DOI | |||||
関連識別子 | 10.1016/j.fusengdes.2015.01.025 | |||||
権利 | ||||||
権利情報 | © 2015 Elsevier B.V. All rights reserved. | |||||
権利 | ||||||
権利情報 | © 2015. This manuscript version is made available under the CC-BY-NC-ND 4.0 | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1016/j.fusengdes.2015.01.025 | |||||
関連名称 | Publisher version | |||||
著者版フラグ | ||||||
出版タイプ | AM | |||||
出版タイプResource | http://purl.org/coar/version/c_ab4af688f83e57aa | |||||
NAIS | ||||||
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