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- Progress in the development of the ICRF system of DTT
This paper describes the design and realisation status of the Ion Cyclotron Range of Frequency (ICRF) system of the Divertor Tokamak Test facility (DTT) DTT requires a large amount of additional heating partially provided by an ICRF system working in the frequency range from 60 to 90 MHz
- The DTT device: system for heating
ICRH, in minority scheme, will produce fast ions, allowing the study of fast particle driven instabilities like alphas in D-T burning plasmas The heating schemes foreseen in DTT are 3He and H minority as well as Deuterium 2nd harmonic
- Analysis of a 8-Strap Plasma-Facing Launcher with Load-Tolerant . . .
This paper reports a preliminary design of the most promising antenna concept for the DTT ICRH system, and the comparison between two load-resilient external matching schemes
- Study of ion cyclotron heating scenarios and fast particles generation . . .
In this study we are investigating the physics of ion-cyclotron resonance heating (ICRH) plasma interaction in the Divertor Tokamak Test facility, on the basis of the plasma and tokamak parameters characterizing the machine, as well as the antenna design
- Design specifications for the ion cyclotron heating amplifier system in . . .
By explaining the reasons behind the adoption of solid-state amplifiers, the paper highlights the role of solid-state technology in advancing fusion research Dive into the research topics of 'Design specifications for the ion cyclotron heating amplifier system in the Divertor Tokamak Test facility' Together they form a unique fingerprint
- Design specifications for the ion cyclotron heating amplifier system in . . .
In the DTT, the ICRH system is primarily intended for heating bulk ions, facilitating H-mode access, and wall conditioning, with a allocated power of 6 MW in the reference configuration, potentially increasing to 9 MW based on initial system results
- (PDF) Design specifications for the ion cyclotron heating amplifier . . .
In the DTT, the ICRH system is primarily intended for heating bulk ions, facilitating H-mode access, and wall condition- ing, with a allocated power of 6 MW in the reference configuration,
- Multiphysics Analysis of High-power Vacuum Feedthrough for DTT ICRH . . .
Abstract: In the framework of the Divertor Tokamak Test (DTT) facility, which aims at the validation of an integrated solution for the power exhaust moving to the DEMOnstration power plant (DEMO), an Ion Cyclotron Resonance Heating (ICRH) system is under development Its final configuration, which comprises two independent modules, shall couple
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