The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mitigate the issue of power exhaust under integrated physics and technical conditions relevant for an International Thermonuclear Experimental Reactor (ITER) and a DEMOnstration Power Plant (DEMO). DTT will be equipped with a 510-keV, 40-A neutral beam injector (NBI) based on negative deuterium ion particles, designed to yield about 10 MW of neutral power to the DTT tokamak. The strongly triangular shape of the beam and the ITER-like multifocusing strategy required a different approach than more conventional solutions in designing the electrostatic plates in order to guarantee the desired beam deflection. This article describes the performance ...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
In parallel with the programme to optimize the operation with a conventional divertor based on detac...
The MITICA experiment will be the full scale prototype of the neutral beam injectors to be installed...
The main purpose of the Divertor Tokamak Test facility (DTT) [1], whose construction is starting in ...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
De Divertor Test Tokamak (DTT) wordt een nieuwe experimentele faciliteit die naar verwachting in de ...
The Divertor Tokamak Test facility (DTT) is the new tokamak whose construction is starting in Frasca...
Neutral beam injectors are the main source of plasma heating in advanced fusion devices. To support ...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
In order to reduce the tritium inventory in a fuel circulation system in fusion plants, a possibilit...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power...
A scheme of a neutral beam injector (NBI), based on electrostatic acceleration and magneto-static de...
The ITER [1] fusion device is expected to demonstrate the feasibility of magnetically confined deute...
ITER neutral beam injector (NBI) is required to produce 1 MeV 16.5 MW neutral beams for 3600 seconds...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
In parallel with the programme to optimize the operation with a conventional divertor based on detac...
The MITICA experiment will be the full scale prototype of the neutral beam injectors to be installed...
The main purpose of the Divertor Tokamak Test facility (DTT) [1], whose construction is starting in ...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
De Divertor Test Tokamak (DTT) wordt een nieuwe experimentele faciliteit die naar verwachting in de ...
The Divertor Tokamak Test facility (DTT) is the new tokamak whose construction is starting in Frasca...
Neutral beam injectors are the main source of plasma heating in advanced fusion devices. To support ...
The Divertor Tokamak Test (DTT) is a new, super-conducting device, being constructed in Frascati, It...
In order to reduce the tritium inventory in a fuel circulation system in fusion plants, a possibilit...
Two Neutral Beam Injectors (NBI) are foreseen to provide a substantial fraction of the heating power...
A scheme of a neutral beam injector (NBI), based on electrostatic acceleration and magneto-static de...
The ITER [1] fusion device is expected to demonstrate the feasibility of magnetically confined deute...
ITER neutral beam injector (NBI) is required to produce 1 MeV 16.5 MW neutral beams for 3600 seconds...
The present ITER NB system includes two design features: short beamline design and vacuum insulated ...
In parallel with the programme to optimize the operation with a conventional divertor based on detac...
The MITICA experiment will be the full scale prototype of the neutral beam injectors to be installed...