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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/10655/00012598a543d205-0817-4dcc-bc6d-8cfd5692e5af
名前 / ファイル | ライセンス | アクション |
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Nucl.Fusion57_pp086046 (6.2 MB)
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Item type | 学術雑誌論文 / Journal Article(1) | |||||
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公開日 | 2021-07-26 | |||||
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× MIYAZAWA, Junichi× TAMURA, Hitoshi× TANAKA, Teruya× GOTO, Takuya× YANAGI, Nagato× SAKAMOTO, Ryuichi× MASUZAKI, Suguru× Ohtani, Hiroaki× 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 |
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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 |