Conveners
Wed-Mo-Po3.02 - Fusion VI: Conductors for Fusion & New Designs
- Andries den Ouden (Radboud University)
- Arnaud Pascal Foussat (CERN)
Second-generation high temperature superconductors (HTS) are available for producing >25 T at magnet bore compared to 16 T for low temperature superconductors (LTS) magnets proposed in recent studies of the Fusion Nuclear Science Facility (FNSF), thus enabling higher fusion power density and a smaller device size. High current density is required for engineering design of the next step FNSF to...
The goal of the Gas-Dynamic Multimirror Trap (GDMT) project is to create a multi-functional experimental facility and lay the groundwork for future development of fusion applications of open-ended magnetic plasma confinement systems with linear axisymmetric configuration. Among the most promising plasma confinement concepts to be studied on this facility are the diamagnetic plasma confinement...
The conceptual design for the superconducting coils of the K-DEMO tokamak has been proposed and continues to be updated. The toroidal field coils rely on Nb3Sn technology with new generation high Jc strand. The design is that of a cable-in-conduit conductor (CICC) consisting of multistage Nb3Sn cable inside a rectangular stainless steel jacket. There are huge Lorentz forces on the cable due...
Conceptual design studies of the helical fusion reactor FFHR-d1 are progressing at National Institute for Fusion Science (NIFS) for realizing steady-state fusion energy production. The continuously wound helical coils have the major radius R of 15.6 m, four times that of the presently working Large Helical Device (LHD) with R = 3.9 m. The High-Temperature Superconducting (HTS)...
The FFHR Design Team has been investigating several types of High-Temperature Superconducting (HTS) large-current capacity conductors to be applied to the LHD-type helical fusion reactor FFHR-d1 (major radius R = 15.6 m). Presently, before realizing this commercial fusion reactor for electricity production, smaller reactors FFHR-c1 (R = 10.92 m) for DEMO and b1 for volumetric neutron source...
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...
