Conveners
WED-OR3-201 Fusion Magnets I
- Hitoshi Tamura (National Institute for Fusion Science)
- Thierry Schild (Iter)
Fusion power plants offer the prospect of a new sustainable source of energy for future generations. The design and R&D of future reactors is expected to largely benefit from the experience gained in the design, construction and operation of ITER. However, deploying reliable fusion power plants, requires to overcome the design challenges and to address the remaining readiness gaps. Europe is...
The Chinese Fusion Engineering Testing Reactor (CFETR) is a DEMO design to bridging the gap between ITER and the first commercial fusion power plant. Toroidal field (TF) magnet system is one of the most challenge for CFETR project. The operating current of the TF magnet is 95.6 kA. The major radius and minor radius of CFETR is designed as 7.2 m and 2.2 m, respectively. To reduce the...
In this study, we focused on the layered winding concept, in which the conductor can be optimized for each layer by grading, and succeeded in the significant improvement of the conventional rectangular conductor winding concept. The radial plate (RP) system is the main proposal for the toroidal field (TF) coil of Japan's DEMO (JA DEMO), because of its performance in ITER. However, the RP...
Tokamak Energy Ltd is a UK company developing spherical tokamaks incorporating HTS magnets in the pursuit of fusion energy production.
A series of demonstration projects has been conducted on a rapid development cycle to generate stable and robust magnet structures, experimental test capabilities, and simulation tools sufficient for the design and construction of a major HTS magnet system...
At the ENEA’s research center of Frascati, the DTT (Divertor Tokamak Test) facility is currently under construction. The activity of this experimental nuclear fusion reactor, will be focused on the optimization of the power exhaust management in view of DEMO. The project has been started during year 2014, when also the superconducting magnet system has been initially designed, basing on the...
The Divertor Tokamak Test facility (DTT) currently under construction at the ENEA Research Center of Frascati, Italy, shall be an experimental fusion reactor that will contribute to the advancement of the EUROfusion roadmap to fusion energy. This work summarizes the design choices and the Finite Element Modelling (FEM) results in support of the Toroidal Field Coil (TFC) system design which is...
The no-insulation (NI) high temperature superconductor (HTS) toroidal field (TF) coil or its variations have been regarded as a potential option for a compact, high magnetic field tokamak due to compactness in size and robustness in operational reliability. However, its real application still faces multiple challenges, e.g., we have limited experience in design, construction, and operation of...
