To improve the efficiency of operation of the tokamak reactor (International Thermonuclear Experimental Reactor, ITER) in future, it is highly desirable to perform a comprehensive validation by numerical simulation of newly-proposed scenarios or controllers before operation. This paper describes the results of the first stage in these simulations, performed for ITER [ITER Technical Basis. ITER EDA Documentation Series No. 24 (IAEA, Vienna, 2002).]. The simulations were carried out using the DINA code [R. R. Khayrutdinov, and V. E. Lukash, Studies of plasma equilibrium and transport in a tokamak fusion device with the inverse-variable technique. Journal of Comp. Physics 107(2) 106 (1993).] with the multiple input-multiple output controllers of plasma current, position and shape developed for ITER. © 2005 Taylor & Francis Group Ltd.
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Condensed Matter Physics