Assessment of the range of controls in JT-60SA plasmas and scenario development
井手 俊介; 相羽 信行; Bolzonella, T.*; Challis, C. D.*; 藤田 隆明; Giruzzi, G.*; Joffrin, E.*; 濱松 清隆; 林 伸彦; 本多 充; 星野 一生; 川島 寿人; 栗田 源一; 松永 剛; 宮田 良明; 仲野 友英; 清水 勝宏; 白石 淳也; 鈴木 隆博; 武智 学; 浦野 創
Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; Hoshino, Kazuo; Kawashima, Hisato; Kurita, Genichi; Matsunaga, Go; Miyata, Yoshiaki; Nakano, Tomohide; Shimizu, Katsuhiro; Shiraishi, Junya; Suzuki, Takahiro; Takechi, Manabu; Urano, Hajime
One of the main goals of JT-60SA project is to achieve steady-state sustainment of a high normalized pressure () plasma, which is required in the ITER steady-stat operation and DEMO. Plasma control plays a key role to accomplish this goal. Assessment of capabilities in controlling key plasma parameters to access and sustain a high plasma in JT-60SA has been carried out using TOPICS with emphasis on controllability with actuators, including not only heating and current drive but also fueling and pumping system. It is confirmed that the safety factor profile can be prepared appropriately at the plasma current ramp-up phase within capability of the installed ECRF system. At the flat-top of a high and high bootstrap current plasma, it is also confirmed that the installed NB system can modify the safety factor profile and the confinement property within the planned capabilities. It is confirmed that impurity seeding in the SOL and the divertor region can maintain the heat flux within the divertor heat tolerance keeping the separatrix density level acceptable.