Add to ORKGThe magnetic, structural, and thermal design of superconducting poloidal field coils for a tokamak fusion-fission breeder reactor are described. The design requirements and considerations, with the resulting parameters, are presented
A choice of various operating modes of a tokamak reactor will have considerable impact on the fatigu...
A superconducting coil system has been developed for the Stellarator fusion reactor. The distributio...
Superconducting magnets for fusion power reactors are discussed. The Large Coil Program for developi...
The design of the Tokamak Fusion Test Reactor (TFTR) Toroidal Field (TF) magnetic coils is described...
A poloidal magnetic field shielding system is proposed for a tokamak EPR. This coil system minimizes...
The manufacturing aspects of two different toroidal field (TF) coils are discussed briefly. The firs...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply...
A conceptual design has been developed for a moderate size (R = 6.0 m) high field (B = 13.1 T at the...
The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply...
A superconducting coil system has been developed for the Stellarator fusion reactor. The distributio...
A conceptual design for a toroidal field (TF) coil for a six coil test array has been developed. The...
A fusion-fission (hybrid) reactor is a combination of a fusion device and a subcritical fission reac...
A choice of various operating modes of a tokamak reactor will have considerable impact on the fatigu...
A superconducting coil system has been developed for the Stellarator fusion reactor. The distributio...
Superconducting magnets for fusion power reactors are discussed. The Large Coil Program for developi...
The design of the Tokamak Fusion Test Reactor (TFTR) Toroidal Field (TF) magnetic coils is described...
A poloidal magnetic field shielding system is proposed for a tokamak EPR. This coil system minimizes...
The manufacturing aspects of two different toroidal field (TF) coils are discussed briefly. The firs...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
In the context of tokamak reactors, the Poloidal Field Coils (PFCs) are magnets that surround the To...
The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply...
A conceptual design has been developed for a moderate size (R = 6.0 m) high field (B = 13.1 T at the...
The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply...
A superconducting coil system has been developed for the Stellarator fusion reactor. The distributio...
A conceptual design for a toroidal field (TF) coil for a six coil test array has been developed. The...
A fusion-fission (hybrid) reactor is a combination of a fusion device and a subcritical fission reac...
A choice of various operating modes of a tokamak reactor will have considerable impact on the fatigu...
A superconducting coil system has been developed for the Stellarator fusion reactor. The distributio...
Superconducting magnets for fusion power reactors are discussed. The Large Coil Program for developi...