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Two conceptual designs of helical fusion reactor FFHR-d1A based on ITER technologies and challenging ideas

http://hdl.handle.net/10655/00012598
http://hdl.handle.net/10655/00012598
a543d205-0817-4dcc-bc6d-8cfd5692e5af
名前 / ファイル ライセンス アクション
Nucl.Fusion57_pp086046.pdf Nucl.Fusion57_pp086046 (6.2 MB)
license.icon
Item type 学術雑誌論文 / Journal Article(1)
公開日 2021-07-26
タイトル
タイトル Two conceptual designs of helical fusion reactor FFHR-d1A based on ITER technologies and challenging ideas
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 HTS
キーワード
主題Scheme Other
主題 liquid blanket
キーワード
主題Scheme Other
主題 molten salt
キーワード
主題Scheme Other
主題 liquid divertor
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 SAGARA, Akio

× SAGARA, Akio

SAGARA, Akio

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MIYAZAWA, Junichi

× MIYAZAWA, Junichi

MIYAZAWA, Junichi
MIYAZAWA, Jun-ichi

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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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YANAGI, Nagato

× YANAGI, Nagato

YANAGI, Nagato

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SAKAMOTO, Ryuichi

× SAKAMOTO, Ryuichi

SAKAMOTO, Ryuichi

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MASUZAKI, Suguru

× MASUZAKI, Suguru

MASUZAKI, Suguru

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Ohtani, Hiroaki

× Ohtani, Hiroaki

Ohtani, Hiroaki

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The FFHR, Design Group

× The FFHR, Design Group

The FFHR, Design Group

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著者ID
内容記述タイプ Other
内容記述 0000-0002-5354-6619
抄録
内容記述タイプ Abstract
内容記述 The Fusion Engineering Research Project (FERP) at the National Institute for Fusion Science (NIFS) is conducting conceptual design activities for the LHD-type helical fusion reactor FFHR-d1A. This paper newly defines two design options, 'basic' and 'challenging.' Conservative technologies, including those that will be demonstrated in ITER, are chosen in the basic option in which two helical coils are made of continuously wound cable-in-conduit superconductors of Nb3Sn strands, the divertor is composed of water-cooled tungsten monoblocks, and the blanket is composed of water-cooled ceramic breeders. In contrast, new ideas that would possibly be beneficial for making the reactor design more attractive are boldly included in the challenging option in which the helical coils are wound by connecting high-temperature REBCO superconductors using mechanical joints, the divertor is composed of a shower of molten tin jets, and the blanket is composed of molten salt FLiNaBe including Ti powers to increase hydrogen solubility. The main targets of the challenging option are early construction and easy maintenance of a large and three-dimensionally complicated helical structure, high thermal efficiency, and, in particular, realistic feasibility of the helical reactor.
書誌情報 Nuclear Fusion

巻 57, 号 8, p. 086046, 発行日 2017-07-17
出版者
出版者 IOP Publishing
出版者
出版者 International Atomic Energy Agency
ISSN
収録物識別子タイプ ISSN
収録物識別子 00295515
書誌レコードID
収録物識別子タイプ NCID
収録物識別子 AA00759871
DOI
関連タイプ isVersionOf
識別子タイプ DOI
関連識別子 10.1088/1741-4326/aa6b12
権利
権利情報 This is the Accepted Manuscript version of an article accepted for publication in Nuclear Fusion. IOP Publishing Ltd is not responsible for any errors or omissions in this version of the manuscript or any version derived from it. The Version of Record is available online at https://doi.org/10.1088/1741-4326/aa6b12
権利
権利情報 (c) 2017, Vienna
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.1088/1741-4326/aa6b12
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
10765
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Cite as

SAGARA, Akio, MIYAZAWA, Jun-ichi, TAMURA, Hitoshi, TANAKA, Teruya, GOTO, Takuya, YANAGI, Nagato, SAKAMOTO, Ryuichi, MASUZAKI, Suguru, Ohtani, Hiroaki, The FFHR, Design Group, 2017, Two conceptual designs of helical fusion reactor FFHR-d1A based on ITER technologies and challenging ideas: International Atomic Energy Agency, 086046– p.

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