| 摘要 |
A toroidal field coil 13 is disclosed for generating a toroidal magnetic field in a nuclear fusion reactor comprising a toroidal plasma chamber having a central column 14. The portion of toroidal field coil 13 passing through the central column 14 comprises: a low temperature superconductor (LTS) layer 21 formed from, for example, niobium-tin or niobium-titanium; a high temperature superconductor (HTS) layer 22 formed from, for example, ReBCO (YBCO or GdBCO), BSCCO 2212, BSCCO 2223, or MgB2, and located radially outward of the LTS layer; and an electrically conducting, non-superconducting material 23, e.g. copper, beryllium or aluminium, located radially outward of the HTS and LTS layers. Neutron shielding 24 may be provided between the hybrid magnet and fusion plasma 11, and insulating vacuum gaps 25 between the different layers of conducting and superconducting material. |
