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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/10655/00012716
5fd1d9c4-280e-44d4-9d8b-fa42f6267904
名前 / ファイル ライセンス アクション
Fus.Eng.Des_98-99_pp1629-1633.pdf 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)
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

TAMURA, Hitoshi

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TANAKA, Teruya

× TANAKA, Teruya

TANAKA, Teruya

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GOTO, Takuya

× GOTO, Takuya

GOTO, Takuya

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MIYAZAWA, Junichi

× MIYAZAWA, Junichi

MIYAZAWA, Junichi
MIYAZAWA, Jun-ichi

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MASUZAKI, Suguru

× MASUZAKI, Suguru

MASUZAKI, Suguru

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WATANABE, Tsuguhiro

× WATANABE, Tsuguhiro

WATANABE, Tsuguhiro

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YANAGI, Nagato

× YANAGI, Nagato

YANAGI, Nagato

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SAGARA, Akio

× SAGARA, Akio

SAGARA, Akio

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ITO, Satoshi

× ITO, Satoshi

ITO, Satoshi

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HASHIZUME1, Hidetoshi

× HASHIZUME1, Hidetoshi

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
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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