MITICA is a prototype of the Heating Neutral Beam (HNB) Injectors for ITER [1]. The MITICA scientific objective is to validate the design and optimize the operating performances of the injector before installation on ITER. The magnetic field configuration in the injector is critical for obtaining the required efficiency and beam optics. In order to quickly achieve the optimal operating condition, it is highly advisable to provide a flexible control of the most critical features of the magnetic field, without opening the vacuum vessel. The possibility of introducing an independent variation of the magnetic field in the plasma source and in the accelerator has been analyzed and a feasible solution proposed, based on small lateral coils. The p...
In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned...
NBImag is a code suitable for the design and opti- mization of complex magnetic field configurations...
The injection of high energy beams of neutral particles is a fundamental method for plasma heating t...
MITICA is a prototype of the Heating Neutral Beam (HNB) Injectors for ITER [1]. The MITICA scientifi...
MITICA is a negative-Ion-based 1 MeV Neutral Beam Injector. The transverse magnetic field in the pla...
MITICA (Megavolt ITER Injector Concept Advancement) is a test facility for the development of a full...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
The work of this PhD thesis has been developed inside the framework of magnetic confinement thermonu...
For ITER heating and current drive, two neutral beam injectors (NBIs) are planned, delivering a tota...
MITICA is the complete full-scale prototype of a 17 MW heating neutral beam injector for ITER. This ...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
The negative ion source of the neutral beam injectors for ITER requires that the co-extracted electr...
MITICA is the complete full-scale prototype of a 17 MW Heating Neutral Beam Injector for ITER. This ...
In the ITER neutral beam injectors (NBI), the presence of an external variable magnetic field genera...
The MITICA Neutral Injector test facility will be constituted by a RF-driven negative Ion Source and...
In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned...
NBImag is a code suitable for the design and opti- mization of complex magnetic field configurations...
The injection of high energy beams of neutral particles is a fundamental method for plasma heating t...
MITICA is a prototype of the Heating Neutral Beam (HNB) Injectors for ITER [1]. The MITICA scientifi...
MITICA is a negative-Ion-based 1 MeV Neutral Beam Injector. The transverse magnetic field in the pla...
MITICA (Megavolt ITER Injector Concept Advancement) is a test facility for the development of a full...
MITICA is a prototype of the heating neutral beam (HNB) Injectors for ITER, built with the purpose o...
The work of this PhD thesis has been developed inside the framework of magnetic confinement thermonu...
For ITER heating and current drive, two neutral beam injectors (NBIs) are planned, delivering a tota...
MITICA is the complete full-scale prototype of a 17 MW heating neutral beam injector for ITER. This ...
The ITER Neutral Beam Test Facility (PRIMA) is presently under construction at Consorzio RFX (Padova...
The negative ion source of the neutral beam injectors for ITER requires that the co-extracted electr...
MITICA is the complete full-scale prototype of a 17 MW Heating Neutral Beam Injector for ITER. This ...
In the ITER neutral beam injectors (NBI), the presence of an external variable magnetic field genera...
The MITICA Neutral Injector test facility will be constituted by a RF-driven negative Ion Source and...
In the framework of the development of the ITER neutral beam (NB) system, a test facility is planned...
NBImag is a code suitable for the design and opti- mization of complex magnetic field configurations...
The injection of high energy beams of neutral particles is a fundamental method for plasma heating t...