Robust Plasma Vertical Stabilization in Tokamak Devices via Multi-objective Optimization

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.

[1]  Gianmaria De Tommasi,et al.  Robust vertical control of ITER plasmas via static output feedback , 2011, 2011 IEEE International Conference on Control Applications (CCA).

[2]  Alfredo Pironti,et al.  ITER-like vertical stabilization system for the east Tokamak , 2017 .

[3]  Claudio Sterle,et al.  Conceptual architecture of the plant system controller for the magnetics diagnostic of the ITER tokamak , 2015 .

[4]  A. Beghi,et al.  Advances in real-time plasma boundary reconstruction: from gaps to snakes , 2005, IEEE Control Systems.

[5]  Massimiliano Mattei,et al.  Control-oriented tools for the design and validation of the JT-60SA magnetic control system , 2017 .

[6]  Alfredo Pironti,et al.  Exploitation of modularity in the JET tokamak vertical stabilization system , 2012 .

[7]  F. W. Gembicki,et al.  Vector optimization for control with performance and parameter sensitivity indices , 1974 .

[8]  D. A. Humphreys,et al.  Plasma current, position and shape feedback control on EAST , 2013 .

[9]  R. Albanese,et al.  XSC Tools: A Software Suite for Tokamak Plasma Shape Control Design and Validation , 2007, IEEE Transactions on Plasma Science.

[10]  H. L. Yang,et al.  Design features of the KSTAR in-vessel control coils , 2009 .

[11]  M. J. D. Powell,et al.  A fast algorithm for nonlinearly constrained optimization calculations , 1978 .

[12]  Robert K. Brayton,et al.  A new algorithm for statistical circuit design based on quasi-newton methods and function splitting , 1979 .

[13]  Alfredo Pironti,et al.  Current, Position, and Shape Control in Tokamaks , 2011 .

[14]  Claudio Sterle,et al.  PIMPA: A Tool for oPtImal Measurement Probes Allocation , 2014, IEEE Transactions on Plasma Science.

[15]  Shih-Ping Han.  A globally convergent method for nonlinear programming , 1975 .

[16]  F. Sartori,et al.  The Joint European Torus , 2006, IEEE Control Systems.

[17]  Gianmaria De Tommasi,et al.  Plasma Vertical Stabilization in the ITER Tokamak via Constrained Static Output Feedback , 2011, IEEE Transactions on Control Systems Technology.

[18]  L. Liu,et al.  A MIMO architecture for integrated control of plasma shape and flux expansion for the EAST tokamak , 2016, 2016 IEEE Conference on Control Applications (CCA).

[19]  Alfredo Pironti,et al.  Magnetic Control of Tokamak Plasmas , 2008 .

[20]  Douglas P. Looze.  Franklin, Powell and Emami-Naeini, Feedback Control of Dynamic Systems, 6 th Edition, Prentice-Hall, 2010. (referred to as FPE) References: Ogata, Modern Control Engineering, Prentice-Hall, 2009. Dorf, Modern Control Systems, Prentice-Hall, 2008. , 2013 .