Conceptual design of the power supplies for DTT Neutral Beam Injector

Ferro, A.; Lucchini, Francesco; Agostinetti, P.; Ratti, Daniele; Granucci, G.; Романо, А.; Romano, Roberto; Cucchiaro, A.; Princiotta, Alessandro

doi:10.1016/j.fusengdes.2021.112624

Cited by 8 publications

(9 citation statements)

References 10 publications

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“…As mentioned earlier, the gas conductivity is due to the presence of positive and negative ion pairs, which in normal situations are generated by the natural radiation. This is taken into account by means of the source parameter S of the transport model ( 6)- (7).…”

Section: A Radiation Induced Conductivitymentioning

confidence: 99%

“…where n is the normal vector to the cathode and j i , a i , b i are extrapolated from experimental observations. Generally the injection phenomenon is referred to electrons, however due to the high electronegativity of the gas, no free electrons are considered in the model ( 6)- (7). These electrons attach themselves to neutral gas molecules thereby increasing the negative ions content.…”

Section: B Relative Humidity Induced Conductivitymentioning

confidence: 99%

“…•s), the injection of negative ions from the metal tip can be included in the drift-diffusion model ( 6)- (7).…”

Section: A Metal Particles Induced Field Emissionmentioning

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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Section: A Radiation Induced Conductivitymentioning

confidence: 99%

Section: B Relative Humidity Induced Conductivitymentioning

confidence: 99%

“…•s), the injection of negative ions from the metal tip can be included in the drift-diffusion model ( 6)- (7).…”

Section: A Metal Particles Induced Field Emissionmentioning

confidence: 99%

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 residual ions can be stripped out of the beam passage by the DM, and they then form a neutral beam that can be injected into the tokamak. According to the different sources of the force on the charged particles during deflection, the deflection methods can be divided into magnetic deflection and electrical deflection [3][4][5]. Currently, the most mature and widely used is the magnetic deflection method.…”

Section: Introductionmentioning

confidence: 99%

Improved Design and Thermo-Mechanical Verification of Deflection Magnet Beam Collimator of EAST-NBI System

Lei

Xie

et al. 2022

Energies

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The deflection magnet (DM) is the most important component of the Neutral Beam Injection (NBI) system of Experimental Advanced Superconducting Tokamak (EAST), which can magnetically deflect the un-neutralized charged particles after the neutralized process of the beam is extracted from the ion source, and then form a neutral beam injected into the tokamak. Under the operating conditions of the NBI system, by using the thermocouple monitoring system in the experiment, it can be found that the currently operating DM beam collimator has a quite high temperature rise. It is necessary to redesign the DM beam collimator to improve its heat transfer performance. The parallel arrangement of multiple rows of tubes is proposed as the basic method for the redesign of the beam collimator of DM, the thermal-fluid-structure analysis model of this redesign model is established and its temperature field, pressure field and stress field are analyzed. Taking the surface temperature of the beam collimator, the overall dimension after the total tube combination and the pressure drop of the whole structure of collimator as the optimization objectives, and setting the fluid velocity, the tube’s inner diameter and the number of tube rows as the design variables, the optimized design scheme of the beam collimator structure is obtained. From the results of simulation, the new structure can better meet the operation requirements of DM, and its maximum temperature rise is well controlled, which is expected to meet the long pulse operation requirements of the NBI system. The proposed simulation and design optimization method can provide a certain reference for the design and optimization of other high-heat-flux structures in complex large-scale neutral beam systems in the future.

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DTT - Divertor Tokamak Test facility: A testbed for DEMO

Ambrosino

2021

Fusion Engineering and Design

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Conceptual design of the power supplies for DTT Neutral Beam Injector

Cited by 8 publications

References 10 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

Improved Design and Thermo-Mechanical Verification of Deflection Magnet Beam Collimator of EAST-NBI System

DTT - Divertor Tokamak Test facility: A testbed for DEMO

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