Artículo
Predictive simulations for plasma scenarios in the SMART tokamak
Autor/es | Mancini, Alessio
Velarde Gallardo, Lina Viezzer, Eleonora Cruz Zabala, Diego José Rivero Rodríguez, Juan Francisco García Muñoz, Manuel Sanchís Sánchez, Lucía Snicker, Antti García Domínguez, J. Segado Fernández, Jorge Hidalgo Salaverri, Javier Cano Megías, Pilar Toscano Jiménez, Manuel |
Departamento | Universidad de Sevilla. Departamento de Ingeniería Energética Universidad de Sevilla. Departamento de Física Atómica, Molecular y Nuclear Universidad de Sevilla. Departamento de Física Aplicada III |
Fecha de publicación | 2023-07 |
Fecha de depósito | 2023-09-05 |
Publicado en |
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Resumen | The SMall Aspect Ratio Tokamak (SMART) is a new spherical machine that is currently being constructed at the University of Seville (Mancini et al., 2021; Agredano-Torres et al., 2021). The operation of SMART will cover ... The SMall Aspect Ratio Tokamak (SMART) is a new spherical machine that is currently being constructed at the University of Seville (Mancini et al., 2021; Agredano-Torres et al., 2021). The operation of SMART will cover three different phases reaching an inductive plasma current ( Iₚ )of more than 500 kA, a toroidal magnetic field ( Bₜ ) of 1 T and a pulse length of 500 ms (Mancini et al., 2021; Agredano-Torres et al., 2021). The main goal of the SMART tokamak is to study high plasma confinement regimes in a broad triangularity range (-0.5 ≤ δ ≤ 0.5) (Doyle et al., 2021; Doyle et al., 2021). While in phase 1 the ohmic heating alone is expected to provide enough power to access the H-mode, in phase 2 and phase 3 the access to the H-mode will be ensured by applying Neutral Beam Injection (NBI) as external heating system. The NBI will consist of one injector at 25 keV and 1 MW of power. The overall design of the NBI, including injection geometry, energy and power have been optimized using the ASCOT5 code (Hirvijoki et al., 2021). The SMART scenarios have been developed with the help of the free boundary equilibrium solver code FIESTA (Cunningham, 2013) coupled to the linear time independent, rigid plasma model RZIP (Lazarus et al., 1990) to calculate the target equilibria for all the different operational phases. To assess the feasibility of those scenarios, predictive modelling needs to be included to evaluate properly the evolution of the temperatures, density profiles for both electrons and ions. To this extent, the 1.5D transport code ASTRA (Pereverzev and Yushmanov, 2002) has been used including models for the ohmic current, bootstrap current and current driven by NBI. This contribution discusses the electron and ion density and temperature profiles obtained for various scenarios for phase 1 and 2 and presents the design study of the NBI. |
Agencias financiadoras | Fondo Europeo de Desarollo Regional (FEDER) by the European Commission under grant agreement number IE17-5670 Fondo Europeo de Desarollo Regional (FEDER) by the European Commission under grant agreement number US-15570 European Union’s Horizon 2020 research and innovation programme grant agreement No. 805162 |
Identificador del proyecto | FEDER IE17-5670
FEDER US-15570 EU H2020 805162 |
Cita | Mancini, A., Velarde Gallardo, L., Viezzer, E., Cruz Zabala, D.J., Rivero Rodríguez, J.F., García Muñoz, M.,...,Toscano Jiménez, M. (2023). Predictive simulations for plasma scenarios in the SMART tokamak. Fusion Engineering and Design, 192 (113833). https://doi.org/10.1016/j.fusengdes.2023.113833. |
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