2000 年 35 巻 7 号 p. 357-362
In the project for the International Thermonuclear Experimental Reactor (ITER), a Central Solenoid (CS) model coil was developed to demonstrate the feasibility of the coil design and fabrication procedure. The model coil was installed in the test facility at JAERI, Naka, and a performance test is being carried out. The cool-down was completed without cold He leakage at the beginning of April 2000. We could charge the model coil up to the nominal current of 46kA without quenching in the first DC charging test. The model coil could generate the maximum field of 13T, and the stored energy was 640MJ. A manual dump test was also performed with the time constant of 5.3s from the nominal current. A maximum voltage of 4.8kV appeared in the coil during the dump test, and no damage was found after the test. In the pulse operation test, the coil could be ramped up to the nominal current in 26s, with the maximum ramping rate of 0.5T/s. The target ramping rate of 0.4T/s was satisfied. The test results are described in this paper.