The mission of Korea Superconducting Tokamak Advanced Research (KSTAR) project is to develop an advanced steady-state superconducting tokamak for establishing a scientific and technological basis for an attractive fus...The mission of Korea Superconducting Tokamak Advanced Research (KSTAR) project is to develop an advanced steady-state superconducting tokamak for establishing a scientific and technological basis for an attractive fusion reactor. Because one of the KSTAR mission is to achieve a steady-state operation, the use of superconducting coils is an obvious choice for the magnet system. The KSTAR superconducting magnet system consists of 16 Toroidal Field (TF) coils and 14 Poloidal Field (PF) coils. Internally-cooled Cable-In-Conduit Conductors (CICC) are put into use in both the TF and PF coil systems. The TF coil system provides a field of 3.5 T at the plasma center and the PF coil system is able to provide a flux swing of 17 V-sec. The major achievement in KSTAR magnet-system development includes the development of CICC,the development of a full-size TF model coil, the development of a coil system for background magnetic-field generation , the construction of a large-scale superconducting magnet and CICC test facility. TF and PF coils are in the stage of fabrication to pave the way for the scheduled completion of KSTAR by the end of 2006.展开更多
Magnetic confinement of thermonuclear plasma ions within a tokamak must be achieved with a finite number of toroidal field(TF) coils. This results in a rippled toroidal field structure, and consequent distortions in f...Magnetic confinement of thermonuclear plasma ions within a tokamak must be achieved with a finite number of toroidal field(TF) coils. This results in a rippled toroidal field structure, and consequent distortions in fast ion orbits with potentially rapid loss of the affected ions. The ripple loss is an important issue for the design of future tokamak reactors such as ITER because it results in reduced alpha heating as well as potentially severe localized wallreactors.展开更多
基金The project supported by the Korea Ministry of Science and Technology under the KSTAR Project
文摘The mission of Korea Superconducting Tokamak Advanced Research (KSTAR) project is to develop an advanced steady-state superconducting tokamak for establishing a scientific and technological basis for an attractive fusion reactor. Because one of the KSTAR mission is to achieve a steady-state operation, the use of superconducting coils is an obvious choice for the magnet system. The KSTAR superconducting magnet system consists of 16 Toroidal Field (TF) coils and 14 Poloidal Field (PF) coils. Internally-cooled Cable-In-Conduit Conductors (CICC) are put into use in both the TF and PF coil systems. The TF coil system provides a field of 3.5 T at the plasma center and the PF coil system is able to provide a flux swing of 17 V-sec. The major achievement in KSTAR magnet-system development includes the development of CICC,the development of a full-size TF model coil, the development of a coil system for background magnetic-field generation , the construction of a large-scale superconducting magnet and CICC test facility. TF and PF coils are in the stage of fabrication to pave the way for the scheduled completion of KSTAR by the end of 2006.
文摘Magnetic confinement of thermonuclear plasma ions within a tokamak must be achieved with a finite number of toroidal field(TF) coils. This results in a rippled toroidal field structure, and consequent distortions in fast ion orbits with potentially rapid loss of the affected ions. The ripple loss is an important issue for the design of future tokamak reactors such as ITER because it results in reduced alpha heating as well as potentially severe localized wallreactors.
