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Progress in design and engineering issues on JA DEMO
https://repo.qst.go.jp/records/83190
https://repo.qst.go.jp/records/83190b599a495-67fe-4d43-851c-ca26a1bd3202
Item type | 会議発表論文 / Conference Paper(1) | |||||
---|---|---|---|---|---|---|
公開日 | 2021-08-06 | |||||
タイトル | ||||||
タイトル | Progress in design and engineering issues on JA DEMO | |||||
言語 | ||||||
言語 | jpn | |||||
資源タイプ | ||||||
資源タイプ識別子 | http://purl.org/coar/resource_type/c_5794 | |||||
資源タイプ | conference paper | |||||
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 |
染谷, 洋二
× 染谷, 洋二× 坂本, 宜照× 日渡, 良爾× 三善, 悠矢× 角舘, 聡× 宇藤, 裕康× 朝倉, 伸幸× 本間, 裕貴× 中島, 徳嘉× 飛田, 健次× Yoji, Someya× Yoshiteru, Sakamoto× Ryoji, Hiwatari× Yuuya, Miyoshi× Satoshi, Kakudate× Hiroyasu, Uto× Nobuyuki, Asakura× Yuuki, Homma× Noriyoshi, Nakajima× Kenji, Tobita |
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抄録 | ||||||
内容記述タイプ | Abstract | |||||
内容記述 | The paper presents solutions for critical problems in Japan’s DEMO (JA DEMO), which include common DEMO design issues beyond ITER-relevant technologies. The main parameters of the reactor are the plasma major radius of ∼8.5m and fusion output of ∼1.5 GW. The highlights of this design study are (i) novel concept for water-cooled pebble bed blanket and tritium extraction, (ii) an outlook of the steady and stable power generation beyond several 100 MW, (iii) all radwastes are classified as LLW (Low Level Waste) and qualified for a shallow land burial, and (iv) identification of an accident sequences and mitigation systems. The proposed concept as JA DEMO will be the foundation for Japan’s DEMO that can be envisioned in the next stage of ITER. | |||||
書誌情報 |
Proceeding 28th IAEA FEC 発行日 2021-05 |