The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization of electricity-producing fusion power plants. ITER has been designed so as to reach the plasma burning condition, and to operate with high elongated unstable plasmas. However, due to the constraints which affect the machine realization, these open-loop unstable high performance plasmas can be hardly stabilized using the Poloidal Field (PF) coils placed outside the tokamak vessel. For this reason, during the ITER design review phase, it has been proposed to investigate the possibility of using in-vessel coils, in order to improve the best achievable performance of the vertical stabilization system. Because of some technological differences bet...
ITER is targeting Q = 10 with 500 MW of fusion power. To meet this target, the plasma needs to be co...
Fusion Advanced Studies Torus (FAST) conceptual study has been proposed as possible European ITER Sa...
The paper deals with the application of the so-called Reference (or Command) Governor constrained co...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
Poloidal field magnetic control in tokamak has the essential functions of stabilizing the vertical i...
In the framework of the ITER project, an investigation has been conducted on an alternative vessel a...
About 85% of the primary energy is currently obtained from fossil sources. In the next future, nucle...
Thermonuclear controlled fusion is a promising answer to the current energy and climate issues, prov...
Historically, tokamak control design has been a combination of theory driving an initial control des...
The capability of the poloidal field coil system, as presently designed, to provide an effective ver...
Key features and main results about the control of the plasma shape in ITER are presented. A control...
Fusion Advanced Studies Torus (FAST) conceptual study has been proposed as possible European ITER Sa...
ITER is targeting Q = 10 with 500 MW of fusion power. To meet this target, the plasma needs to be co...
Fusion Advanced Studies Torus (FAST) conceptual study has been proposed as possible European ITER Sa...
The paper deals with the application of the so-called Reference (or Command) Governor constrained co...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
Poloidal field magnetic control in tokamak has the essential functions of stabilizing the vertical i...
In the framework of the ITER project, an investigation has been conducted on an alternative vessel a...
About 85% of the primary energy is currently obtained from fossil sources. In the next future, nucle...
Thermonuclear controlled fusion is a promising answer to the current energy and climate issues, prov...
Historically, tokamak control design has been a combination of theory driving an initial control des...
The capability of the poloidal field coil system, as presently designed, to provide an effective ver...
Key features and main results about the control of the plasma shape in ITER are presented. A control...
Fusion Advanced Studies Torus (FAST) conceptual study has been proposed as possible European ITER Sa...
ITER is targeting Q = 10 with 500 MW of fusion power. To meet this target, the plasma needs to be co...
Fusion Advanced Studies Torus (FAST) conceptual study has been proposed as possible European ITER Sa...
The paper deals with the application of the so-called Reference (or Command) Governor constrained co...