Japanese perspective of fusion nuclear technology from ITER to DEMO

Japanese endeavors to establish technological bases for DEMO

“…Basic strategy in Future Fusion R&D [1] is robust and has been reconfirmed by the investigation of the Joint-Core Team. In addition, this strategy is embodied beyond the previous analyses [5,6] so as to accelerate implementation of related programs.…”

“…and current drive systems(5) Theory and numerical simulation research (6) Reactor plasma research (7) Fuel Systems (8) Material development and establishment of codes and standards (9) Safety of DEMO and safety research (10) Availability and maintainability (11) Diagnostics and control systems, all related research and development programs are organized in Chart of Establishment of Technological Bases for DEMO around the development of the design of DEMO as the primary axis with attention paid to required evidence to support the maturity of the design of DEMO and consistency in the timeline.…”

Evolution of the ITER program and prospect for the next-step fusion DEMO reactors: status of the fusion energy R&D as ultimate source of energy

“…Preliminary design studies of DEMO reactors have been performed by several groups in a fusion thermal output range of 1500-5000 MW [28][29][30][31][32]. Key elements so far learned from these studies are the dense and stable plasma, the tritium breeding blanket system, scheduled maintenance scenario of the in-vessel components such as blanket modules and diverters keeping a reasonable availability [32,33].…”

Numerical Simulation of a No-Insulation BSCCO Toroidal Magnet Applied in Magnetic Confinement Fusion

“…With the development in the properties of high temperature superconducting (HTS) conductors, the HTS magnet could be considered as potential Tokamak magnet components with the advantages of higher operation temperature and critical current density [1][2][3]. At present, the application of HTS in fusion devices mainly focuses on the design and fabrication of high temperature superconducting high current conductor [4][5][6][7][8], the design and fabrication of high temperature superconducting current lead [9,10], and the concept design and small model fabrication of HTS magnet [11,12]. It was revealed that when the TF coil system operates at the temperature range of 10 to 20 K, accordingly, the manufacturing and operating cost of the device could be reduced [13].…”