Optimization of JT-60SA plasma operational scenario with capabilities of installed actuators
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; 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; JT-60SA Research Plan Contributors; JT-60SAチーム
Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; Kawashima, Hisato; Kurita, Genichi; Matsunaga, Go; Miyata, Yoshiaki; Nakano, Tomohide; Shimizu, Katsuhiro; Shiraishi, Junya; Suzuki, Takahiro; Takechi, Manabu; Urano, Hajime; JT-60SA Research Plan Contributors; JT-60SA Team
Assessment of capabilities in controlling key plasma parameters to access and sustain a high normalized pressure plasma in JT-60SA has been carried out using predictive simulations 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, which is believed to play an important role for confinement improvement, can be prepared appropriately at the plasma current ramp-up phase in a wide extent within capability of the installed ECRF system. At the flat-top of a high pressure 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.