Improved Conceptual Design of the Beamline for the DTT Neutral Beam Injector

Agostinetti, Piero; Benedetti, E.L.; Bonifetto, Roberto; Bonesso, M.; Cavenago, M.; Bello, S. Dal; Palma, M. Dalla; D’Ambrosio, Domenic; Dima, R.; Favero, Giacomo; Ferro, A.; Fincato, M.; Giorgetti, F.; Granucci, G.; Lombroni, R.; Marconato, N.; Marsilio, Roberto; Murari, A.; Patton, T.; Pavei, M.; Pepato, A.; Pilan, N.; Raffaelli, F.; Rebesan, Pietro; Recchia, M.; Ripani, M.; Романо, А.; Sartori, E.; Tinti, P.; Valente, M.; Variale, V.; Ventura, Giulio; Veronese, F.; Zanino, R.; Zavarise, Giorgio

doi:10.1109/tps.2022.3162902

Cited by 10 publications

(7 citation statements)

References 23 publications

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“…INFN is contributing to the development of several components of DTT, i.e. the Neutral Beam Injector (NBI) source [26], the NBI accelerator [27], the RF system [28], the interferometry/polarimetry plasma diagnostics [29], the reflectometry plasma diagnostics [30] and the soft X-ray plasma diagnostics. It is worth emphasizing that in the development of the NBI accelerator as well as the RF transmission systems and launchers, extensive use of the Additive Manufacturing technology is being pursued, specifically studying how to optimize the procedure in order to get the best material characteristics and performances.…”

Section: The Magnetic Confinement Fusion Roadmapmentioning

confidence: 99%

Applications of nuclear physics to energy: the INFN-E project of the National Institute of Nuclear Physics (INFN)

Ripani

2024

J. Inst.

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In this talk, the main issues in radioactive waste management worldwide will be briefly introduced, as well as the world roadmap towards nuclear fusion. Then, an overview of the activities of the INFN-E (INFN Energia) strategic project will be given, showing how INFN's skills on basic theoretical aspects and on the design, construction and use of accelerators and radiation detectors can be applied to specific projects for the characterization and monitoring of radioactive waste as a means to increase nuclear safety and in the context of advanced plants for the study of nuclear fusion.

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Section: The Magnetic Confinement Fusion Roadmapmentioning

confidence: 99%

Applications of nuclear physics to energy: the INFN-E project of the National Institute of Nuclear Physics (INFN)

Ripani

2024

J. Inst.

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“…Differently from the ITER NBI, whose ion source is located in vacuum, for the reason that will be clarified in the following, the design of the NBI for DTT has characteristics similar to that of the JT-60 experiment and foresees an air-insulated beam source, which simplifies the design phase and increases its reliability and maintenance [8]. Therefore, the electrical connection between the TL and the acceleration grids is performed through bus-bars connected to the SF 6air high voltage bushing, as illustrated in Fig.…”

Section: A Radiation Induced Conductivitymentioning

confidence: 99%

“…In fact the typical pulse length is about 10-30 s for conventional NBIs, while for the ITER NBI, whose full-scale prototype MITICA (Megavolt ITER Injector and Concept Advancement) is being under construction at the PRIMA (Padova Research on ITER Megavolt Accelerator) test facility in Padua, Italy [2], the pulse length will be extended up to 3600 s. The NBI that will operate in the Divertor Tokamak Test facility (DTT) [3], [4], the construction of which is in the start phase in Frascati, Italy, has similar requirements to the one installed in JT-60SA [5] and is expected to operate with a duty cycle of 50 s every hour with a beam energy of 500 keV and 10 MW of power coupled to the plasma. In this configuration the negative Deuterium ions are accelerated by three Acceleration Grids (AGs) with -167 kV DC per stage [6], [7], [8]. Lastly, some of the HVDC-GIS components are exposed to the radiation (neutrons and γ s) coming from the Tokamak, thus affecting the electrical conductivity of the insulating gas.…”

Section: Introductionmentioning

confidence: 99%

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Development of HVDC Gas-Insulated Components for the Power Supply of Neutral Beam Injectors

Lucchini

Marconato²

2023

IEEE Access

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The development of High Voltage Direct Current Gas-Insulated components that will be employed for the power supply of Neutral Beam Injectors, requires specific numerical tools to analyze the electric field distribution, with the purpose of supporting the engineering and operational phases.The tools must comply with the nonlinearity of the material properties of solid insulators and the transport mechanisms in the dielectric gas. Despite its high Global Warming Potential, SF6 will be considered as the baseline dielectric gas for the development of HVDC gas-insulated components to be used for the Acceleration Grid Power Supply of Neutral Beam Injectors. Attention especially to the mechanisms driving to an increase of leakage current flowing in the gas, thus giving rise to possible discharge phenomena is here placed, mainly focusing on radiation and injection regimes. The described methodologies are adopted for the numerical modeling of the 500 kV DC gas-insulated components that will be used for the power supply of the Neutral Beam Injector of the Divertor Tokamak Test facility. In particular, a conceptual design of the SF6 Transmission Line and the SF6-air bushing is conceived.INDEX TERMS Divertor tokamak test (DTT), neutral beam injector, HVDC, gas insulated transmission lines, high voltage bushing.

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“…For the vacuum pumping, it is foreseen to have a system based on turbo-molecular pumps located on the side walls of the vessel and Non-Evaporable Getter (NEG) pumps located on the upper and lower surfaces of the vessel. More information on the conceptual design of the beamline for DTT NBI can be found in [12].…”

Section: Introductionmentioning

confidence: 99%