The design and R&D for ITER In-Vessel Coils (IVCs) is being deployed. The concerned issue of “Edge Localized Modes” (ELMs) and “Vertical Stabilization” (VS) of the ITER plasma can be addressed by the implemented IVCs. The ELM and VS coils will be installed in the vessel just behind the blanket shield modules to reach the requirement of keeping strong coupling with the plasma. The 59mm Stainless Steel Jacketed Mineral Insulated Conductor (SSMIC) using MgO as the insulation is being designed for the IVCs to resist the special challenges, including the nuclear radiation, high temperature, electromagnetic and thermal fatigue. It is necessary to take the mechanical performances of the SSMIC and the feasibility of fabrication techniques into consideration of the R&D program. The mechanical performances of the SSMIC close to the actual work conditions, including the three point bend modulus, three point bend cyclical performance and the cyclical performance with a U-bend sample of the SSMIC prototypes have been investigated and the results are presented in this paper.
- Nuclear Engineering Division
Mechanical Performances of ITER In-Vessel Coil’s Conductor
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Jin, H, Yu, W, Long, F, Yu, M, Han, Q, & Zhai, Y. "Mechanical Performances of ITER In-Vessel Coil’s Conductor." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering. Chengdu, China. July 29–August 2, 2013. V005T14A020. ASME. https://doi.org/10.1115/ICONE21-16887
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