A common problem of the multi-beamlet, negative-ion based Heating Neutral Beam (HNB) Injectors presently used in fusion research, is the undesired deflection of negative ions due the permanent magnets embedded in the Extraction Grid (EG) for the suppression of the unwanted co-extracted electrons. A new solution has been recently developed at Consorzio RFX, which makes use of an additional set of permanent magnets, also embedded in the EG, with a series of advantages in terms of performances and versatility with respect to the traditional electrostatic compensation. This solution is now the new standard for ITER. After a thorough validation of the design by different numerical models, it was decided to experimentally test this solution for t...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
Abstract. To meet the requirements of the four operating and one start-up scenarios foreseen in the ...
To reach fusion conditions and control the plasma configuration in ITER, the next step in tokamak fu...
During 2016, a joint experimental campaign was carried out by QST and Consorzio RFX on the Negative ...
NIO1 is a compact source of negative ions jointly developed by RFX and INFN, to study the physics of...
Maintenance-free RF sources for negative hydrogen ions with moderate extraction areas (100-200 cm2) ...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
The development of the NBI systems for ITER requires unprecedented parameters (40A of negative ion c...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
The negative ion source of the neutral beam injectors for ITER requires that the co-extracted electr...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
NBImag is a code suitable for the design and opti- mization of complex magnetic field configurations...
The NIO1 experiment is a compact and modular negative ion source built at Consorzio RFX, Padua, with...
In the framework of the collaboration between Consorzio RFX (Padova, Italy) and QST (Naka, Japan) tw...
The next fusion project DEMO, which will be the evolution of the experimental fusion reactor [Intern...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
Abstract. To meet the requirements of the four operating and one start-up scenarios foreseen in the ...
To reach fusion conditions and control the plasma configuration in ITER, the next step in tokamak fu...
During 2016, a joint experimental campaign was carried out by QST and Consorzio RFX on the Negative ...
NIO1 is a compact source of negative ions jointly developed by RFX and INFN, to study the physics of...
Maintenance-free RF sources for negative hydrogen ions with moderate extraction areas (100-200 cm2) ...
A joint Japan-EU R&D activity is in progress to optimize the accelerator for the ITER NBI. The accel...
The development of the NBI systems for ITER requires unprecedented parameters (40A of negative ion c...
International audienceA joint Japan-EU R&D activity is in progress to optimize the accelerator for t...
The negative ion source of the neutral beam injectors for ITER requires that the co-extracted electr...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
NBImag is a code suitable for the design and opti- mization of complex magnetic field configurations...
The NIO1 experiment is a compact and modular negative ion source built at Consorzio RFX, Padua, with...
In the framework of the collaboration between Consorzio RFX (Padova, Italy) and QST (Naka, Japan) tw...
The next fusion project DEMO, which will be the evolution of the experimental fusion reactor [Intern...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
Abstract. To meet the requirements of the four operating and one start-up scenarios foreseen in the ...
To reach fusion conditions and control the plasma configuration in ITER, the next step in tokamak fu...