Integrated modeling of toroidal rotation with the NTV and boundary models for JT-60U analyses and ITER simulations
JT-60U解析とITERシミュレーションのためのNTVと境界条件モデルを考慮したトロイダル回転の統合モデリング
本多 充; 佐竹 真介*; 鈴木 康浩*; 吉田 麻衣子; 林 伸彦; 神谷 健作; 松山 顕之; 篠原 孝司; 松永 剛; 仲田 資季; 井手 俊介; 浦野 創
Honda, Mitsuru; Satake, Shinsuke*; Suzuki, Yasuhiro*; Yoshida, Maiko; Hayashi, Nobuhiko; Kamiya, Kensaku; Matsuyama, Akinobu; Shinohara, Koji; Matsunaga, Go; Nakata, Motoki; Ide, Shunsuke; Urano, Hajime
The integrated framework for toroidal momentum transport in a tokamak plasma is developed, which self-consistently calculates the neoclassical toroidal viscosity (NTV), the radial electric field and resultant toroidal rotation together with the scrape-off-layer (SOL) physics-based boundary model. The coupling of three codes, TOPICS, which is an integrated tokamak transport code developed in JAEA, VMEC, which is a 3D equilibrium solver, and FORTEC-3D, which is a 3D neoclassical transport solver developed in National Institute for Fusion Science, can calculate rotation caused by the NTV due to the non-axisymmetric perturbed magnetic field stemming from toroidal field coils. It is found that the NTV influences toroidal rotation in JT-60U and holds the key to determine the NTV profile. The sensitivity of the toroidal rotation profile to the boundary rotation necessitates the boundary condition modeling. From the measurement in JT-60U, the gradient is found to be virtually zero at the separatrix. Focusing on , the toroidal momentum boundary model is developed in conjunction with the SOL/divertor plasma code. This modeling realizes self-consistent predictive simulations for operation scenario development in ITER.