DTT - Divertor Tokamak Test facility: A testbed for DEMO

Ambrosino, R.

doi:10.1016/j.fusengdes.2021.112330

Cited by 65 publications

(39 citation statements)

References 27 publications

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“…Moreover, due to the pulsed operation of NBIs, the HVDC-GIS are not in steady state operation. 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].…”

Section: Introductionmentioning

confidence: 99%

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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Section: Introductionmentioning

confidence: 99%

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

Lucchini

Marconato²

2023

IEEE Access

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“…In the framework of the European Roadmap to Nuclear Fusion [1], the DTT (Divertor Tokamak Test) facility [2] is currently under construction at ENEA, Frascati. The machine is fully superconductive [3], similarly to the largest tokamaks in operation (e.g.…”

Section: Introductionmentioning

confidence: 99%

Techno-Economic Optimization of the NbTi DTT Feeders

et al. 2023

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The superconducting (SC) coils of the Divertor Tokamak Test (DTT) facility will be connected to the current leads by a set of SC feeders, currently designed as cable-in-conduit conductors wound using commercial NbTi strands to be cooled by Supercritical Helium at 4.5 K. The feeders are immersed in the magnetic field generated by the SC coil and plasma outside of magnet system, so that the maximum field on the most loaded feeder can reach 4 T at the full rated current (including the self-field effect). Here the performance of the feeder conductors is assessed during a plasma pulse, based on the DTT standard singlenull operating scenario, for the most loaded feeder of the Central Solenoid and of the Toroidal and Poloidal Field coils, computing the minimum temperature margin to current sharing throughout the plasma scenario. Several alternative cabling configurations are analyzed, designed to withstand the nominal current at the peak field with a different number of SC and stabilizer strands. A figure of merit is built parametrically based on the variation of the minimum temperature margin as a function of the material, manufacturing and operational costs of the different alternative feeder layouts. Based on such techno-economical characterization, the optimal (cheapest) design of the feeder cables is identified.INDEX TERMS DTT facility, Superconducting cables, Cable-in-conduit conductors, current leads, temperature margin, techno-economic analysis FIGURE 1. Layout of the SC feeders and cryolines for the DTT machine: CSCL: Central Solenoid Current Leads box; PFCL: Poloidal Field Current Leads box; and TFCL (bottom left) Toroidal Field Current Leads box.

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“…However, this process becomes highly demanding from an engineering point of view, and relaxed design criteria are highly desirable. This work is particularly relevant to the research effort in magnetically confined fusion plasmas, as gyrotrons are foreseen to play a major role in heating, current drive, and instability control of fusion plasmas 20 in tokamaks, such as ITER 21 , DDT 22 , or DEMO 23 , and in stellarators such as Wendelstein 7-X 24 .…”

Section: Introductionmentioning

confidence: 99%

Self-consistent formation and steady-state characterisation of trapped high energy electron clouds in the presence of a neutral gas background

Bars¹,

Hogge²,

Loizu³

et al. 2022

Preprint

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This study considers the self-consistent formation and dynamics of electron clouds interacting with a background neutral gas through elastic and inelastic (ionisation) collisions in coaxial geometries similar to gyrotron electron guns. These clouds remain axially trapped as the result of crossed magnetic field lines and electric equipotential lines creating potential wells similar to those used in Penning traps. Contrary to standard Penning traps, in this study we consider a strong externally applied radial electric field which is of the same order as that of the space-charge field. In particular, the combination of coaxial geometry, strong radial electric fields and electron collisions with the residual neutral gas (RNG) present in the chamber induce non-negligible radial particle transport and ionisation. In this paper, the dynamics of the cloud density and currents resulting from electron-neutral collisions are studied using a 2D3V particle-in-cell code. Simulation results and parametric scans are hereby presented. Finally, a fluid model is derived to explain and predict the cloud peak density and peak radial current depending on the externally applied electric and magnetic fields, and on the RNG pressure.

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DTT - Divertor Tokamak Test facility: A testbed for DEMO

Cited by 65 publications

References 27 publications

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

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

Techno-Economic Optimization of the NbTi DTT Feeders

Self-consistent formation and steady-state characterisation of trapped high energy electron clouds in the presence of a neutral gas background

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