Pool-cooled superconducting magnet design of large helical device
Abstract
The Large Helical Device is the next generation in helical equipment for nuclear fusion. The large scale superconducting magnets are going to be applied to these coils. The major and minor radius of the helical coil system are 4 and 0.96 m respectively and the magnetic field is 4 T at the plasma center and 8 T at the coil surface. The coil system stores about 2 GJ of total energy. The superconductor of the helical coil is pure aluminum stabilized Nb-Ti compacted strand cable with copper housing. The coils have a stainless-steel helium can that is filled with liquid helium. This pool-cooled superconducting helical coil system satisfies the fully stabilized condition. The superconducting poloidal coils are composed of six (three pairs) circular coils and use forced-cooled superconductors to reduce the eddy current losses by the field changing operation. The helical and poloidal coil system are built in the large bell-jar (vacuum vessel for thermal insulation) with outer diameter of 13 m. Conductor design and stability of superconducting magnets for helical and poloidal coil systems are described.
- Publication:
-
Plasma Physics and Controlled Nuclear Fusion: Next Generation Experiments in Helical Systems
- Pub Date:
- March 1990
- Bibcode:
- 1990ppcn.conf..147S
- Keywords:
-
- Controlled Fusion;
- Cooling Systems;
- Field Coils;
- Helical Windings;
- Heliotrons;
- Reactor Design;
- Stellarators;
- Superconducting Magnets;
- Eddy Currents;
- Magnetic Fields;
- Plasma Control;
- Thermal Insulation;
- Vacuum Chambers;
- Plasma Physics