A predictive study of non-inductive current driven KSTAR tokamak discharge modes using a new transport/heating simulation package
Myunghee Ju; Jinyong Kim; KSTAR Team; Myunghee Ju; Korea Basic Science Institute, Yusong-Ku, Taejon, Korea; Jinyong Kim; Korea Basic Science Institute, Yusong-Ku, Taejon, Korea; KSTAR Team; Korea Basic Science Institute, Yusong-Ku, Taejon, Korea
Журнал:
Nuclear Fusion
Дата:
2000-11-01
Аннотация:
For the physical objectives of the KSTAR tokamak, a predictive transport/heating/current drive simulation package has been developed and named ASTRA/LSC/TORIC. A new simulation package consists of the ray tracing lower hybrid wave code LSC, a neutral beam Fokker-Planck solver and the ICRF full wave code TORIC together with the transport code ASTRA. The new simulation package ASTRA/LSC/TORIC can be applied to many interesting research areas such as heating and non-inductive current drive physics for a steady state plasma, predictive study of advanced tokamak modes with a, for example, high beta, high H factor and high bootstrap current. Studies into two kinds of question are made: (a) Can the total required plasma current I<sub>p</sub> (a baseline heating mode with 1.5 MA and an upgrade heating mode with 2.0 MA) be driven fully non-inductively and be sustained during a flat-top phase of reasonable KSTAR reference plasma parameter ranges with the help of auxiliary KSTAR heating (H) and current drive (CD) systems (NBH/CD, LHH/CD and ICRH/CD)? (b) Can a reversed shear mode be developed in an early ramp-up phase and be sustained during a flat-top phase? These predictive simulation results using a newly developed simulation package are presented.
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