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Japan's Efforts to Develop the Concept of JA DEMO During the Past Decade
https://repo.qst.go.jp/records/76084
https://repo.qst.go.jp/records/76084d0e04adc-58ed-4cb0-a2a4-9f29e35695fa
| 名前 / ファイル | ライセンス | アクション |
|---|---|---|
Japan s Efforts to Develop the Concept of JA DEMO.pdf (3.4 MB)
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| Item type | 学術雑誌論文 / Journal Article(1) | |||||
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| 公開日 | 2019-05-08 | |||||
| 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 | |||||
| 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 |
飛田, 健次
× 飛田, 健次× 日渡, 良爾× 坂本, 宜照× 染谷, 洋二× 朝倉, 伸幸× 宇藤, 裕康× 三善, 悠矢× 徳永, 晋介× 本間, 裕貴× 角舘, 聡× 中島, 徳嘉× 原型炉設計合同特別チーム× Tobita, Kenji× Hiwatari, Ryoji× Sakamoto, Yoshiteru× Someya, Yoji× Asakura, Nobuyuki× Uto, Hiroyasu× Miyoshi, Yuuya× Tokunaga, Shinsuke× Homma, Yuuki× Kakudate, Satoshi× Nakajima, Noriyoshi |
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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 of 8.5 m and fusion power of 1.5-2 GW based on water-cooled solid breeding (WCSB) blanket with PWR water condition (290-325ºC, 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, 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. Breeding blanket (BB) design has been concentrated on simplification of the internal structure and pressure tightness of BB casing against in-box LOCA (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 came 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, p. 372-383, 発行日 2019-06 |
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| 出版者 | ||||||
| 出版者 | Taylor and Francis | |||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 1536-1055 | |||||
| DOI | ||||||
| 識別子タイプ | DOI | |||||
| 関連識別子 | 10.1080/15361055.2019.1600931 | |||||
| 関連サイト | ||||||
| 識別子タイプ | URI | |||||
| 関連識別子 | https://www.tandfonline.com/doi/full/10.1080/15361055.2019.1600931 | |||||
