Speaker
Description
In this article, we presented a technical design of the superconducting Dipole magnet, H-type like the SAMURAI magnet at RIKEN, for the Lithium(Li) alloy, the material of first wall of ITER Demo, magnetofluid behaver study, depending on mechanics, thermal and electromagnetic multi-field couple analyze results. Each coil has 1998 turns, with the inner diameter was 1.5m. The wire has NbTi filaments with a total Cu/SC ratio of about 8 in the conductor. The operating current and the goal of central field are 425A and 3.0T, within 1000mm×1000mm×300mm(L×W×H) regions the inhomogeneity of the field is less than 5%, and the maximal magnetic field (Bmax) is 4.3T in the coils, respectively. The vertical magnetic force in the coils is about 200 tons, and the maximal hoop stress and radial stress of the coils are about 90MPa and 10MPa, theoretically. Meanwhile, magnetic quality and coil’s stress state affected by the assembly error and welding deformation of the magnet former are systematical analyzed, moreover dependent on the previous correlation results, we optimized the manufacture and assemble parameters to reduce the cast. And the cold mass of each coil is suspended from the room temperature vacuum vessel by six Titanium alloy suspension links. The magnet, with energy stored in the magnet is about 5 MJ, will be self-protecting. However, in order to limit the temperature, current and voltage value under a reasonable value in case of a quench, multi-segments protection method was employed. Now, the magnet is under construction, and as expected the test results will be reported.
