ITER scenario development with TSC code

Miyamoto, Seiji; Nakamura, Yukiharu*; Toshimitsu, Shinichi; Sugie, Tatsuo; Kusama, Yoshinori; Yoshino, Ryuji; Hayashi, Nobuhiko; Oyama, Naoyuki; Takenaga, Hidenobu; Oikawa, Toshihiro*

Development of ITER operation scenario using TSC code in JAEA is reviewed. TSC is a numerical code to simulate plasma evolution solving the MHD equation in an axisymmetric cylindrical coordinates. We have incorporated numerical models of electron cyclotron heating (ECH) / current drive (ECCD) and neutral beam injection (NBI) heating / current drive into the TSC code. Using the incorporated ECH/ECCD model, flux saving during plasma current ramp-up by EC is discussed. It is shown that resistive flux is effectively reduced due to heating of electron by EC. Recently, we are incorporating a neutral particle fueling and pumping model for studying effect of H-L transition on the poloidal field coil system of ITER size machine. A plan of neutral model development in TSC is also presented.