China
Africa
Explore chapters and articles related to this topic
Field reversed configuration (FRC)
Published in S. V. Ryzhkov, A. Yu. Chirkov, Alternative Fusion Fuels and Systems, 2018
The simplest spherical FRC model is called Hill’s vortex [132]. FRC is sometimes called a compact toroidal configuration [123], because it has a toroidal geometry (closed magnetic field lines), but also open field lines of force. In FRC, just like in a tokamak, a huge current flows through the plasma, but it does not create a holding poloidal magnetic field (as in a tokamak). The poloidal field is formed in the FRC by means of external coils, the azimuthal current is a consequence of the reversal of the magnetic field.
Outer Divertor Damage Characterization from Deuterium Plasma Bombardment in Graphene-Coated Tungsten in the C-2W Device
Published in Fusion Science and Technology, 2019
Marcos X. Navarro, Marziyeh Zamiri, Martin E. Griswold, John F. Santarius, Gerald L. Kulcinski, Max Lagally, Toshiki Tajima
An excellent balance between potential reactor attractiveness and technical development risk motivates the development of field-reversed configuration (FRC) fusion power plants.1,2 The linear, cylindrical FRC geometry facilitates the design of shields, magnets, input-power systems, and tritium-breeding blankets, while the high FRC (≡plasma pressure/magnetic field pressure) increases the plasma power density and allows a compact fusion core. The surface heat flux to the divertor is moderate despite a high-power density because the plasma flowing to the end chamber walls carries much of the charged-particle fusion power. The computer-aided design (CAD) of the Tri Alpha Energy (TAE Technologies) FRC experimental facility,3–5 known both as C-2W and Norman, is shown in Fig. 1. The FRC is an approximately ellipsoidal magnetic configuration immersed inside the magnetic field lines of an open-ended magnetic geometry. The open field lines guide charged particles toward the inner or end divertors for carrying heat and removing impurities from the system. Therefore, it is important to characterize the damage to the divertor surfaces due to the particle and heat fluxes.