DocumentCode :
325033
Title :
Physics and engineering aspects of the ICRF heating and current drive system on KSTAR
Author :
Hong, B.G. ; Ju, M.H. ; Bae, Y.D. ; Kwak, J.G. ; Han, J.M. ; Mau, T.K. ; Swain, D.W. ; Carter, M.D. ; Ryan, P.M.
Author_Institution :
Korea Atomic Energy Res. Inst., Taejon, South Korea
Volume :
1
fYear :
1997
fDate :
6-10 Oct 1997
Firstpage :
469
Abstract :
The design of an ICRF heating and current drive system was undertaken as part of the KSTAR (Korea Superconducting Tokamak Advanced Research) design study. ICRF fast wave heating and current drive scenarios are identified and modelled using the full wave code, TORIC which solves the finite Larmor radius wave equations in the ion cyclotron frequency range in an arbitrary axisymmetric toroidal geometry. The characteristics of the fast wave propagation/absorption, power partitions among plasma species, and the driven current/current drive efficiencies are analysed. The ICH/FWCD launcher is designed to have four current straps and each strap, using appropriate tuning, matching, and decoupling circuitry will be driven by an independent 2 MW RF power source. We present the design characteristics of the ICH/FWCD launcher, and the matching and decoupling system. Also, the feasibility of the antenna design to couple the required power to the plasma is demonstrated
Keywords :
antennas in plasma; fusion reactor design; fusion reactor ignition; plasma electromagnetic wave propagation; plasma radiofrequency heating; plasma simulation; plasma toroidal confinement; 2 MW; ICH/FWCD launcher; ICRF heating; KSTAR; Korea Superconducting Tokamak Advanced Research; TORIC code; antenna design; axisymmetric toroidal geometry; current drive system; decoupling circuitry; design study; engineering aspects; fast wave heating; fast wave propagation; finite Larmor radius wave equations; full wave code; fusion reactors; physics aspects; power partitions; Cyclotrons; Heat engines; Heating; Partial differential equations; Physics; Plasma properties; Plasma sources; Power system modeling; Solid modeling; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
Type :
conf
DOI :
10.1109/FUSION.1997.687082
Filename :
687082
Link To Document :
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