Neutral beam injectors are the main source of plasma heating in advanced fusion devices. To support the realization and optimize the performances of the injectors of ITER tokamak, a dedicated test bed is under construction at Consorzio RFX, Padova. This facility will include a full scale prototype of the injector, named megavolt ITER injector concept advancement. Its aim is to demonstrate and optimize a 16-MW neutral beam power, obtained by neutralization of a 56-A deuterium negative ion beam D 12 accelerated to an energy of 1 MeV. Since the expected current density available at the source is 3c300 A/m2, a large extraction area is needed in order to obtain the required current, so that the beam is formed by the superposition of 1280 beamle...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1MV...
Neutral beam injectors are the main source of plasma heating in advanced fusion devices. To support ...
The MITICA experiment will be the full scale prototype of the neutral beam injectors to be installed...
Neutral beam injection is the main method for plasma heating in magnetic confinement fusion devices....
The injection of high energy beams of neutral particles is a fundamental method for plasma heating t...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
The megavolt ITER injector and concept advancement experiment is the prototype and the test bed of t...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
MITICA (Megavolt ITER Injector Concept Advancement) is a test facility for the development of a full...
The development of the NBI systems for ITER requires unprecedented parameters (40A of negative ion c...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
For ITER heating and current drive, two neutral beam injectors (NBIs) are planned, delivering a tota...
In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1MV...
Neutral beam injectors are the main source of plasma heating in advanced fusion devices. To support ...
The MITICA experiment will be the full scale prototype of the neutral beam injectors to be installed...
Neutral beam injection is the main method for plasma heating in magnetic confinement fusion devices....
The injection of high energy beams of neutral particles is a fundamental method for plasma heating t...
The main purpose of the Divertor Tokamak Test (DTT) facility is to study alternative solutions to mi...
The megavolt ITER injector and concept advancement experiment is the prototype and the test bed of t...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
MITICA (Megavolt ITER Injector Concept Advancement) is a test facility for the development of a full...
The development of the NBI systems for ITER requires unprecedented parameters (40A of negative ion c...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
For ITER heating and current drive, two neutral beam injectors (NBIs) are planned, delivering a tota...
In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1MV...