on different electrical and mechanical joint concepts are required, as well as the construction of a facility which could wind and test a fusion-relevant HTS TF coil. Because much of the remaining work is engineering development as opposed to basic R&D, with adequate resources the time horizon for this technology to achieve its goal would be 3-6 years. Most of the infrastructure to build and test benchtop-scale joints already exists, primarily at the National High Field Magnet Lab and at MIT. An HTS coil winding facility would be advantageous for compact, high-field research in general as well as benefitting joint research. The only country besides the US which has been seriously investigating demountable joints is Japan, through the NIFS, although this program is also limited in scope. Thus, there is a large gap in global development in which the US could become world leaders in this technology. [1] Sorbom, B. N., et al. "ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets." Fusion Engineering and Design 100 (2015): 378-405. [2] Yanagi, N., Ito, S., Terazaki, Y., Seino, Y., Hamaguchi, S., Tamura, H., Sagara, A. (2015). Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor. Nuclear Fusion, 55(5), 53021. [3] Mangiarotti, Franco Julio. Design of demountable toroidal field coils with REBCO superconductors for a fusion reactor. Diss. Massachusetts Institute of Technology, 2016. [4] Ito, S., Seino, Y., Yanagi, N., Terazaki, Y., Sagara, A., & Hashizume, H. (2014). Bridge-Type Mechanical Lap Joint of a 100 kA-Class HTS Conductor having Stacks of GdBCO Tapes, 9(3405086). [5] Mangiarotti, F. J., & Minervini, J. V. (2015). Advances on the design of demountable toroidal field coils with REBCO superconductors for an ARIES-I class fusion reactor. IEEE Transactions on Applied Superconductivity, 25(3).
on different electrical and mechanical joint concepts are required, as well as the construction of a facility which could wind and test a fusion-relevant HTS TF coil. Because much of the remaining work is engineering development as opposed to basic R&D, with adequate resources the time horizon for this technology to achieve its goal would be 3-6 years. Most of the infrastructure to build and test benchtop-scale joints already exists, primarily at the National High Field Magnet Lab and at MIT. An HTS coil winding facility would be advantageous for compact, high-field research in general as well as benefitting joint research. The only country besides the US which has been seriously investigating demountable joints is Japan, through the NIFS, although this program is also limited in scope. Thus, there is a large gap in global development in which the US could become world leaders in this technology. [1] Sorbom, B. N., et al. "ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets." Fusion Engineering and Design 100 (2015): 378-405. [2] Yanagi, N., Ito, S., Terazaki, Y., Seino, Y., Hamaguchi, S., Tamura, H., Sagara, A. (2015). Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor. Nuclear Fusion, 55(5), 53021. [3] Mangiarotti, Franco Julio. Design of demountable toroidal field coils with REBCO superconductors for a fusion reactor. Diss. Massachusetts Institute of Technology, 2016. [4] Ito, S., Seino, Y., Yanagi, N., Terazaki, Y., Sagara, A., & Hashizume, H. (2014). Bridge-Type Mechanical Lap Joint of a 100 kA-Class HTS Conductor having Stacks of GdBCO Tapes, 9(3405086). [5] Mangiarotti, F. J., & Minervini, J. V. (2015). Advances on the design of demountable toroidal field coils with REBCO superconductors for an ARIES-I class fusion reactor. IEEE Transactions on Applied Superconductivity, 25(3).
FESAC_TEC_Demountable_Coils.docx