@misc{oai:repo.qst.go.jp:00072775,
 author = {Asakura, Nobuyuki and Hoshino, Kazuo and Uto, Hiroyasu and Someya, Yoji and Suzuki, Satoshi and Bachmann, Christian and Reimerdes, Holger and Tokunaga, Shinsuke and Kudo, Hironobu and Homma, Yuuki and Sakamoto, Yoshiteru and Hiwatari, Ryoji and Wenninger, Ronald and Tobita, Kenji and Federicic, Gianfranco and Ezato, Koichiro and Seki, Yoji and Ohno, Noriyasu and Ueda, Yoshio and 朝倉 伸幸 and 星野 一生 and 宇藤 裕康 and 染谷 洋二 and 鈴木 哲 and 徳永 晋介 and 工藤 広信 and 本間 裕貴 and 坂本 宜照 and 日渡 良爾 and 飛田 健次 and 江里 幸一郎 and 関 洋治},
 month = {Sep},
 note = {Power exhaust scenario and divertor design for a steady-state Japan (JA) DEMO and a pulse Europe (EU) DEMO1 have been investigated as one of the most important common issues in Broader Approach DEMO Design Activity. Radiative cooling is a common approach for the power exhaust scenario. For the JA DEMO, development of the divertor design appropriate for high Psep/Rp ~30 MWm-1 is required, while the radiation fraction in the main plasma (fradmain = Pradmain/Pheat) is ITER-level (0.40-0.45) and the exhaust power above the L- to H-mode power threshold (fLH = Psep/PthLH) is large margin (~2). For the EU DEMO1, larger fradmain (= 0.67) and smaller fLH (=1.2) plasma is required, using higher-Z impurity seeding, in order to apply ITER-level divertor (Psep/Rp = 17 MWm-1). ITER technology, i.e. water cooling with W-monoblock and Cu-alloy (CuCrZr) heat sink, is a baseline for JA and EU to handle the peak heat load of 10 MWm-2-level, and neutron flux and irradiation dose are comparable. For the JA DEMO, two different water-cooling pipes, i.e. CuCrZr and F82H steel, are proposed. For the EU DEMO1, the heat sink consists of all Cu-alloy pipe, and the divertor size is reduced with replacing the baffles by the breeding blankets. Choices of the heat sink components have been developed appropriate to the high irradiation dose condition. These JA and EU approaches of the power exhaust scenario will provide important case studies for the future decision of the DEMO divertor design., The 13the International Symposium on Fusion Nuclear Technology(ISFNT-13)},
 title = {Plasma Exhaust and Divertor Studies in JA and EU Broader Approach,  DEMO Design Activity},
 year = {2017}
}