B.G. Hong , M.H. Ju, Y.D. Bae, J.G. Kwak, J.M. Han, T.K. Mau*. D. W. Swain^, M.D. Carter^, and P.M. Ryan^
Korea Atomic Energy Research Institute, P.O. Box 105, Yusong, Taejon, Korea 350-600.
* University of California at San Diego, La Jolla, CA 92093.
^ Oak Ridge National Laboratory, Oak Ridge, TN 37831.
The design of an ICRF heating and current drive system was undertaken as a part of the KSTAR(Korea Superconducting Tokamak Advanced Research) [1] design study. One of the KSTAR research objectives is to explore the methods to achieve steady state operation using non-inductive current drive for tokamak fusion reactors.
ICRF fast wave heating and current drive scenarios are identified for the advanced tokamak operation and modelled using the full wave code, TORIC[2] which solves the finite Larmor radius wave equations in the ion cyclotron frequency range in an arbitrary axisymmetric to roidal geometry. The characteristics of the fast wave propagation/absorption, power partitions among plasma species and the driven current/current drive efficiencies are analysed. The effect of the poloidal magnetic field on kxx is treated in self-consistent manner by using a Grad-Shafranov equilibrium solution.
The ICH/FWCD launcher has four current straps and each strap, using appropriate tuning, matching, and decoupling circuitry will be driven by an independent RF power source. The goal of the IC system is to deliver up to 6 MW of power to the plasma under a variety of plasma conditions. The system will be upgraded to provide 12 MW of power to the plasma with the addition of a second system. We present the design characteristics of the ICH/FWCD launcher and the matching and decoupling system. Also, the feasibility of the design to couple the required power to the plasma is demonstrated.
[1] G. S. Lee et al. Bulletin of the American Physical Society, Vol 41, No. 7, p1439,1996.
[2] M. Brambilla, ``A Full Wave Code for Ion Cyclotron Waves in Toroidal Plasma,'' Report IPP 5/66,
Garching (1996).