Full Paper
IAEA-CN77
Contents  Return  Previous Page  Next Page  Index


Return To: Session FT/P2 - Engineering Design
Prev Page: (FT/P2-01) Key Features and Progress of the KSTAR
Next Page: (FT/P2-03) HT-7U Superconducting Tokamak: Physics Design, Engineering Progress


(FT/P2-02) Progress in Development of KSTAR Heating and Current Drive Systems for Long Pulse Operation

B.G. Hong1), B.H. Oh1), W. Namkung2), Y.D. Bae1), Y.S. Bae2), M.H. Cho2), C.K. Hwang1), S.R. In1), S.H. Jeong1), J.G. Kwak1), K.W. Lee1), J.S. Yoon1)
 
1) Korea Atomic Energy Research Institute, Daejeon, Korea
2) Pohang University of Science and Technology, Pohang, Korea

Abstract.  The heating and current drive systems for the KSTAR tokamak are being developed to support long pulse, high beta, advanced tokamak fusion physics experiments. The heating and current drive systems consist of neutral beam injection (NBI) and radio frequency (RF) systems, and they have to be able to operate for long pulse lengths up to 300 sec. The flexibility to provide a range of control functions including current drive and profile control derives from the use of multiple heating technologies: tangential NBI (beam energy < 120 keV, 8 MW), ion cyclotron waves (frequency range of 25-60 MHz, 6 MW), and lower hybrid waves (frequency of 5.0 GHz, 1.5 MW). Development of high power, long pulse relevant heating and current drive technologies for each system are underway.

Read the full paper in PDF format.

IAEA 2003