Abstract
In this paper we present a robust design procedure for plasma vertical stabilization systems in tokamak fusion devices. The proposed approach is based on the solution of a multi-objective optimization problem, whose solution is aimed at obtaining the desired stability margins under different plasma operative scenarios. The effectiveness of the proposed approach is shown by applying it to the ITER-like vertical stabilization system recently tested on the EAST tokamak.
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Notes
- 1.
The tokamak concept was first developed in the former Soviet Union in the early 1960s. Indeed, the name tokamak stems from the Russian words for toroidal chamber and magnetic coil, which is toroidalnaya kamera i magnitnaya katiushka.
- 2.
The speed gain is multiplied by \(I_{p_{ref}}\) in order to scale the overall gain according to the actual value of the plasma current.
- 3.
The plasma linear models exploited to solve the optimization problem are generated by the CREATE magnetic equilibrium codes [9].
- 4.
When computing the open loop transfer function, the simplified model of the power supply of the in-vessel circuit is also considered.
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De Tommasi, G., Mele, A., Pironti, A. (2017). Robust Plasma Vertical Stabilization in Tokamak Devices via Multi-objective Optimization. In: Sforza, A., Sterle, C. (eds) Optimization and Decision Science: Methodologies and Applications. ODS 2017. Springer Proceedings in Mathematics & Statistics, vol 217. Springer, Cham. https://doi.org/10.1007/978-3-319-67308-0_31
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DOI: https://doi.org/10.1007/978-3-319-67308-0_31
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