@article{oai:repo.qst.go.jp:00076084,
 author = {飛田, 健次 and 日渡, 良爾 and 坂本, 宜照 and 染谷, 洋二 and 朝倉, 伸幸 and 宇藤, 裕康 and 三善, 悠矢 and 徳永, 晋介 and 本間, 裕貴 and 角舘, 聡 and 中島, 徳嘉 and 原型炉設計合同特別チーム and Tobita, Kenji and Hiwatari, Ryoji and Sakamoto, Yoshiteru and Someya, Yoji and Asakura, Nobuyuki and Uto, Hiroyasu and Miyoshi, Yuuya and Tokunaga, Shinsuke and Homma, Yuuki and Kakudate, Satoshi and Nakajima, Noriyoshi},
 journal = {Fusion Science and Technology},
 month = {Jun},
 note = {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.},
 pages = {372--383},
 title = {Japan's Efforts to Develop the Concept of JA DEMO During the Past Decade},
 volume = {75},
 year = {2019}
}