Conveners
Wed-Af-Or26: Joints and AC loss for Fusion Magnets
- Arend Nijhuis (University of Twente)
- Sylvie Nicollet (CEA)
The US Domestic Agency (USDA) is the supplier of the Central Solenoid (CS) for ITER. The ITER CS uses three different types of joints. In order to verify the joint performance in close to the operational conditions, the USDA built a test sample that contains all three types of CS joints in order to test it in the SULTAN facility. The SULTAN facility allows testing under a variable DC magnetic...
CFETR which stands for “China Fusion Engineering Test Reactor” is a new tokamak device to be built in China as a complimentary to ITER device. Its magnet system includes the Toroidal Field (TF), Center solenoid (CS) and Poloidal Field (PF) coils. The central solenoid consists of 6 coils consisting of Nb3Sn strands to be operated at a maximum magnetic field of about 14 T.
Among several...
The superconducting coils of the ITER tokamak have hundreds of joints interconnecting conductor unit lengths. The joints operate in magnetic field of up to 4T, field derivatives up to 0.5T/s, and currents up to 70kA. The majority of the joints has a twin-box design, with the exception of the coaxial and splice joints of the Central Solenoid. They are designed differently, to fit into the tight...
Segment-fabrication of high-temperature superconducting (HTS) coils has been proposed for huge and complex superconducting magnets. In Japan, the LHD-type helical fusion reactor, FFHR, designed by National Institute for Fusion Science, adopts the segment-fabrication for its helical coils as the challenging option. The fabrication method is called "joint-winding", in which the HTS helical coils...
Abstract: The Poloidal Field (PF) magnet system of the International Thermonuclear Experimental Reactor (ITER) consists of six pulsed coils. Each coil comprises independent modules connected with “shaking hands” lap-type joints. The feasibility and stability of the plasma scenario requires the magnets to retain sufficient current and temperature margin. The joints essentially represent the...
The design of ITER Poloidal Coils contains 88 joints connecting individual conductors. Satisfying restrictions from operating condition, manufacturability and serviceability, these joints were designed as twin-box “shaking hands” concept. To ensure the manufacturing process consistently produces acceptable components, joint qualification tests have been defined for AC losses, DC resistance,...