Coils and power supplies design for the SMART tokamak

Agredano-Torres, M.; García-Sánchez, Jorge Luis; Mancini, A.; Doyle, Scott; García-Muñoz, M.; Ayllon-Guerola, J.; Barragán-Villarejo, Manuel; Viezzer, E.; Segado-Fernández, J.; Lopez-Aires, D.; Toledo-Garrido, J.J.; Buxton, P.F.; Chung, Kyoung−Jae; García-Domínguez, J.; Garcia-Franquelo, L.; Gryaznevich, M.; Hidalgo-Salaverri, J.; Hwang, Y.S.; Leon-Galvan, J.I.; Ortega, José María Maza

doi:10.1016/j.fusengdes.2021.112683

Cited by 22 publications

(7 citation statements)

References 7 publications

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“…A central solenoid is used to drive inductive current [19]. The main (toroidal) magnetic field is generated through 12 rectangular toroidal field (TF) coils [9]. Initial operation (Phase I) will be limited to on-axis field B 0 ⩽ 0.1T.…”

Section: The Smart Devicementioning

confidence: 99%

“…Another possible mechanism for NB ions loss are ripple perturbations to the static magnetic field caused by the finite number of TF coils. Based on the geometry and number of the coils, the TF ripple field amplitude is up to 1% at the plasma edge on the low-field side, and rapidly decreases to ≪1% inside the plasma, cf figures 7 and 8 in [9]. Orbit simulations are performed to assess the NB ion losses associated with TF ripple for a worst-case scenario with negative triangularity, in which the plasma region on the low-field side is maximized.…”

Section: Simulations For Nbi Optimizationmentioning

confidence: 99%

“…To that end, the SMall Aspect Ratio Tokamak (SMART [6]) device is being commissioned at the University of Seville (Spain). The main goal of SMART is to test experimentally the potential advantages of negative triangularity scenarios in a ST configuration [6][7][8][9][10], and contribute to the overall understanding of the physics and transport scaling of ST-based fusion devices in terms of plasma confinement [11]. Experimental data will also provide valuable information for further development and validation of predictive transport models.…”

Section: Introductionmentioning

confidence: 99%

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NBI optimization on SMART and implications for scenario development

Podestà,

Cruz-Zabala,

Poli

et al. 2024

Plasma Phys. Control. Fusion

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The SMall Aspect Ratio Tokamak (SMART) under commissioning at the University of Seville, Spain, aims to explore confinement properties and possible advantages in confinement for compact/spherical tokamaks operating at negative vs. positive triangularity. This work explores the benefits of auxiliary heating through Neutral Beam Injection (NBI) for SMART scenarios beyond the initial Ohmic phase of operations, in support of the device’s mission. Expected values of electron and ion temperature achievable with NBI heating are first predicted for the current flat-top phase, including modeling to optimize the NBI injection geometry to maximize NBI absorption and minimize losses for a given equilibrium. Simulations are then extended for a selected case to cover the current ramp-up phase. Differences with results obtained for the flat-top phase indicate the importance of determining the plasma evolution over time, as well as self-consistently determining the edge plasma parameters for reliable time-dependent simulations. Initial simulation results indicate the advantage of auxiliary NBI heating to achieve nearly double values of pressure and stored energy compared to Ohmic discharges, thus significantly increasing the device’s performance. The scenarios developed in this work will also contribute to diagnostic development and optimization for SMART, as well as providing test cases for initial predictions of macro- and micro-instabilities.

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Section: The Smart Devicementioning

confidence: 99%

Section: Simulations For Nbi Optimizationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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NBI optimization on SMART and implications for scenario development

Podestà,

Cruz-Zabala,

Poli

et al. 2024

Plasma Phys. Control. Fusion

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“…It is found in the literature [13] that the electrical conductivity of plasma changes with plasma temperature. As plasma is kept at a very high temperature inside a Tokamak, which can then moderately vary in an unpredictable manner, it is naturally concerning to assume the electrical conductivity of plasma σ p to be a fixed and known quantity.…”

Section: Robust Optimal Control Problemmentioning

confidence: 99%

“…A similar analytical approach was also mentioned in the book [1]. Apart from the analytical studies, experimentally motivated papers on Tokamak and Stellarator that are very important for Modelling a Tokamak are well existed in the literature [13,14,15,16,17,18,19,20,21]. The existence of turbulence on the outer part of Tokamak plasma brings hindrance against achieving the steady stable plasma state, thereby attracting a significant number of researchers to address this issue in their relevant papers [21,17,14].…”

mentioning

confidence: 99%

A Note on Optimal Tokamak Control for Fusion Power Simulation

Holst¹,

Kungurtsev²,

Mukherjee³

2022

Preprint

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The Tokamak device is the most promising candidate for producing sustainable electric power by nuclear fusion. It is a torus-shaped device that confines plasma by a strong magnetic field. The development, design and control of the design has been an important area of research, and a significant target is to effectively confine the extremely hot plasma inside its hollow torus-shaped body without touching its boundary for a prolonged period of time. In an attempt to control a Tokamak device, this paper investigates an optimal control problem for an incompressible, viscous, electrically conducting MHD fluid confined in a closed toroidal region in the presence of an applied current. The objective functional for the optimal control problem are subject to set of constraint equations, Navier-Stokes and Maxwell equations. We target the transient control of guiding the plasma to a desired flow at a particular short time instant, where it is expected that the flow had been designed offline to be the desired one from the point of view of steady state operation.

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