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Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade
http://hdl.handle.net/10655/00013169
http://hdl.handle.net/10655/00013169644010fa-9240-4d46-8c98-04aa2f9eab34
Item type | 学術雑誌論文 / Journal Article(1) | |||||
---|---|---|---|---|---|---|
公開日 | 2022-05-25 | |||||
タイトル | ||||||
タイトル | Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade | |||||
言語 | ||||||
言語 | eng | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | DEMO | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | fusion reactor | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | diverter | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | blanket | |||||
キーワード | ||||||
主題Scheme | Other | |||||
主題 | radioactive waste | |||||
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 | |||||
アクセス権 | ||||||
アクセス権 | metadata only access | |||||
アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
著者 |
TOBITA, Kenji
× TOBITA, Kenji× HIWATARI, Ryoji× SAKAMOTO, Yoshiteru× SOMEYA, Youji× ASAKURA, Nobuyuki× UTOH, Hiroyasu× MIYOSHI, Yuya× TOKUNAGA, Shinsuke× HOMMA, Yuki× KAKUDATE, Satoshi× NAKAJIMA, Noriyoshi× the Joint Special Design Team for Fusion DEMO |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | This paper summarizes the evolution of Japanese DEMO design studies in a retrospective manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently working on the conceptual study of a steady-state DEMO (JA DEMO) with a major radius Rp of 8.5 m and fusion power Pfus of 1.5 to 2 GW based on water-cooled solid breeding blanket with pressurized water reactor water condition (290ºC to 325ºC, 15.5 MPa). Such a lower Pfus allows to find realistic design solutions for divertor heat removal. Recognizing that divertor heat removal is one of the most challenging issues on DEMO, the divertor design has been carried out in different approaches, including numerical divertor plasma simulation, magnetic configurations, heat sink design, etc. It is noteworthy that the latest divertor simulation led to a design window allowing divertor heat removal of the peak heat flux of <10 MW/m2. The breeding blanket (BB) design has been concentrated on simplification of the internal structure and pressure tightness of the BB casing against the in-box loss-of-coolant accident. Due to a large amount of radioactive waste generated in periodic replacement of in-vessel components, downsizing of waste-related facilities has come to be regarded as a significant design issue. A possible waste management for reducing temporary waste storage was proposed, and its impact on the plant layout was assessed. | |||||
書誌情報 |
Fusion Science and Technology 巻 75, 号 5, p. 372-383, 発行日 2019-05-07 |
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書誌的事項 | ||||||
the 23rd Topical Meeting on the Technology of Fusion Energy—Licensing, New Facilities, and Safety | ||||||
出版者 | ||||||
出版者 | Taylor & Francis | |||||
ISSN | ||||||
収録物識別子タイプ | ISSN | |||||
収録物識別子 | 15361055 | |||||
書誌レコードID | ||||||
収録物識別子タイプ | NCID | |||||
収録物識別子 | AA11558871 | |||||
DOI | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1080/15361055.2019.1600931 | |||||
情報源 | ||||||
関連名称 | Kenji Tobita, Ryoji Hiwatari, Yoshiteru Sakamoto, Youji Someya, Nobuyuki Asakura, Hiroyasu Utoh, Yuya Miyoshi, Shinsuke Tokunaga, Yuki Homma, Satoshi Kakudate, Noriyoshi Nakajima & the Joint Special Design Team for Fusion DEMO (2019) Japan’s Efforts to Develop the Concept of JA DEMO During the Past Decade, Fusion Science and Technology, 75:5, 372-383, DOI: 10.1080/15361055.2019.1600931 | |||||
関連サイト | ||||||
識別子タイプ | DOI | |||||
関連識別子 | https://doi.org/10.1080/15361055.2019.1600931 | |||||
関連名称 | Publisher version |