Article
Magnetic equilibrium design for the SMART tokamak
Author/s | Doyle, S. J.
López-Aires, D. Mancini, Alessio Agredano Torres, Manuel García Sánchez, J. L. Segado Fernández, Jorge Ayllón Guerola, Juan Manuel ![]() ![]() ![]() ![]() ![]() ![]() ![]() García Muñoz, Manuel ![]() ![]() ![]() ![]() ![]() ![]() ![]() Viezzer, Eleonora ![]() ![]() ![]() ![]() ![]() ![]() ![]() Soria del Hoyo, Carlos ![]() ![]() ![]() ![]() ![]() ![]() ![]() García López, J Cunningham, G. |
Department | Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear Universidad de Sevilla. Departamento de Electrónica y Electromagnetismo Universidad de Sevilla. Departamento de Ingeniería Mecánica y de Fabricación |
Publication Date | 2021 |
Deposit Date | 2021-09-14 |
Published in |
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Abstract | The SMall Aspect Ratio Tokamak (SMART) device is a new compact (plasma major radius Rgeo≥0.40 m, minor radius a≥0.20 m, aspect ratio A≥1.7) spherical tokamak, currently in development at the University of Seville. The SMART ... The SMall Aspect Ratio Tokamak (SMART) device is a new compact (plasma major radius Rgeo≥0.40 m, minor radius a≥0.20 m, aspect ratio A≥1.7) spherical tokamak, currently in development at the University of Seville. The SMART device has been designed to achieve a magnetic field at the plasma center of up to Bϕ=1.0 T with plasma currents up to Ip=500 kA and a pulse length up to τft=500 ms. A wide range of plasma shaping configurations are envisaged, including triangularities between −0.50≤δ≤0.50 and elongations of κ≤2.25. Control of plasma shaping is achieved through four axially variable poloidal field coils (PF), and four fixed divertor (Div) coils, nominally allowing operation in lower-single null, upper-single null and double-null configurations. This work examines phase 2 of the SMART device, presenting a baseline reference equilibrium and two highly-shaped triangular equilibria. The relevant PF and Div coil current waveforms are also presented. Equilibria are obtained via an axisymmetric Grad-Shafranov force balance solver (Fiesta), in combination with a circuit equation rigid current displacement model (RZIp) to obtain time-resolved vessel and plasma currents. |
Project ID. | US-15570
![]() IE17-5670 ![]() 805162 ![]() |
Citation | Doyle, S.J., López-Aires, D., Mancini, A., Agredano Torres, M., García Sánchez, J.L., Segado Fernández, J.,...,Cunningham, G. (2021). Magnetic equilibrium design for the SMART tokamak. Fusion Engineering and Design, Article number 112706. |
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