The Central Solenoid (CS) Model Coil project was started in 1992 as one of the most important R & D programs in the International Thermal Experimental Reactor (ITER) Engineering Design Activity (EDA). The purpose is to confirm the design criteria and performance of the ITER conductor, to develop and verify manufacturing tooting and processes, and to verify material performance following fabrication processes. The CS model coil was fabricated by using full-size ITER CS conductor and consisted of an inner module of 10 layers and an outer module of 8 layers. The coil, which has an inner diameter of 1.58m, an outer module of 3.6m, and a height of 2.78m, including two 0.5m lead regions. The coil was completed in 1999 and tested at the CS model coil test facility in JAERI in 2000. It achieved successfully 13T at 46kA under the pulsed operation condition of 0.4T/s for a ramp-up rate and 1.2T/s for a ramp-down rate, which is targeted as development. And the CS insert, which was a one-layer solenoid to investigate the performance of the ITER conductor in detail, was constructed and tested by being installed inside the CS model coil. The inset was operated up to 13T with a ramp-up rate of 1.2T/s.
To demonstrate the superconducting magnet technology applicable for the construction of the International Thermonuclear Experimental Reactor (ITER), a model coil simulating the ITER central solenoid coil has been fabricated. In this way, the world's largest superconducting pulse coil with supercritical helium forced-flow cooling was realized. To test the model coil, the Japan Atomic Energy Research Institute has developed and constructed a large superconducting coil test facility named the CS model coil test facility. This facility has a large power supply system with a maximum capacity of 225MVA and a 5kW helium cryogenic system with a 1.0kg supercritical helium circulation system, which is the world's largest superconducting test facility. Design features, specifications, and performances of the CS model coil test facility are described.
In International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities, the Central Solenoid Model Coil (CSMC) and the CS Insert Coil (CSIC) have been fabricated, and installed into the ITER CSMC test facility at Naka Fusion Establishment, Japan Atomic Energy Research Institute (JAERI). The CSMC and CSIC conductors are applied to the cable-in-conduit conductors cooled by forced-flow supercritical helium (SHe) at 4.5K. There are 48 parallel cooling channels for the