Interaction of high-energy neutral beams with Divertor Tokamak Test plasma

Vincenzi, P.; Agostinetti, P.; Ambrosino, R.; Bolzonella, T.; Casiraghi, I.; Castaldo, A.; Piccoli, C. De; Granucci, G.; Mantica, P.; Pigatto, L.; Snicker, A.; Vallar, M.

doi:10.1016/j.fusengdes.2023.113436

Cited by 7 publications

(2 citation statements)

References 13 publications

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“…DTT will also be equipped with a negative ion based NBI system with a single injector able to inject up to 10 MW of power into the plasma. The deuterium beam is designed to reach an energy ⩽510 keV, to operate effectively at high densities [42]. The injector installation is planned for the 2032.…”

Section: General Settings Of Core Simulationsmentioning

confidence: 99%

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Casiraghi

Mantica

Ambrosino

et al. 2023

Plasma Phys. Control. Fusion

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Deuterium plasma discharges of the Divertor Tokamak Test facility (DTT) in diﬀerent operational scenarios have been predicted by a comprehensive ﬁrst-principle based integrated modelling activity using state-of-art quasi-linear transport models. The results of this work refer to the updated DTT conﬁguration, which includes a device size optimisation (enlargement to R0 = 2.19 m and a = 0.70 m) and upgrades in the heating systems. The focus of this paper is on the core modelling, but special attention was paid to the consistency with the SOL parameters required to achieve divertor plasma detachment. The compatibility of these physics-based predicted scenarios with the electromagnetic coil system capabilities was then veriﬁed. In addition, ﬁrst estimates of DTT sawteeth and of DTT ELMs were achieved.

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Section: General Settings Of Core Simulationsmentioning

confidence: 99%

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Casiraghi

Mantica

Ambrosino

et al. 2023

Plasma Phys. Control. Fusion

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“…Neutral beam injection with hydrogen isotope (H/D/T) has been demonstrated as an effective plasma heating and current drive (H&CD) method in many magnetic confined fusion devices in service [1][2][3][4][5][6][7], and is still favorable for future fusion development [8][9][10][11]. As the fusion device scaling up, the required injecting particle energy is higher and higher to attain a better H&CD effect on the core plasma.…”

Section: Introductionmentioning

confidence: 99%

Study on stray electrons ejecting from a long-pulse negative ion source for fusion

Yang,

Wei,

et al. 2024

Plasma Phys. Control. Fusion

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The negative ion based neutral beam injection (NNBI) is a desirable plasma heating and current drive method for the large-scale magnetic fusion devices. Due to the strict requirements and difficult development of the negative ion source for fusion, a long-pulse negative ion source has been developed under the framework of the Comprehensive Research Facility for Fusion Technology (CRAFT) in China. This negative ion source consists of a single RF driver plasma source and a three-electrode accelerator. The typical extraction and acceleration voltage are 4~8 kV and 40~50 kV, respectively.During one shot of the long-pulse (~100 s) beam extraction, the gas pressure in the vacuum vessel increased sharply and the temperature of the cryopump rise from 8 K to 20 K. Moreover, the vessel wall appeared a high temperature after several long-pulse shots. A self-consistent simulation of beam-gas interaction revealed that the heat loads on the vessel wall should be caused by the stray electrons ejecting from the accelerator. Those stray electrons are mainly generated via the stripping or ionization collisions and strongly deflected by the downstream side of the deflection magnetic field for the co-extracted electron. The location of hot spots measured by infrared thermography is consistent with the simulation results. To solve this problem, a series of electron dumps are designed to avoid the direct impinging of the ejecting electrons on the cryopump and the vessel wall. And the results suggest that the hot spots are almost eliminated.

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Optimization of a large-area grid electrode for negative ion source in fusion neutral beam injector

Wang,

Yang

et al. 2024

Nuclear Engineering and Technology

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Interaction of high-energy neutral beams with Divertor Tokamak Test plasma

Cited by 7 publications

References 13 publications

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling

Study on stray electrons ejecting from a long-pulse negative ion source for fusion

Optimization of a large-area grid electrode for negative ion source in fusion neutral beam injector

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