ITER shape controller and transport simulations

• Published in: Fusion engineering and design Vol. 83; no. 2; pp. 552 - 556
• Main Authors: Casper, T.A., Meyer, W.H., Pearlstein, L.D., Portone, A.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01.04.2008; New York, NY Elsevier Science
• Subjects: Applied sciences; Controled nuclear fusion plants; Controllers; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Free-boundary; Installations for energy generation and conversion: thermal and electrical energy; ITER; Simulation; Transport; Controllers; ITER; Simulation; Transport; Free-boundary; Tokamak; Plasma; Nuclear fusion reactor; Modeling
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2007.09.009

We currently use the CORSICA integrated modeling code for scenario studies for both the DIII-D and ITER experiments. In these simulations, free- or fixed-boundary equilibria are simultaneously converged with thermal evolution determined from transport models providing temperature and current density profiles. Using a combination of fixed boundary evolution followed by free-boundary calculation, we determine the separatrix and coil currents. We use free-boundary evolution with a state-space controller representation and transport simulation to provide feedback modeling of shape, vertical stability and profile control. In addition to a tightly coupled calculation with simulator and controller imbedded inside CORSICA, we also use a remote procedure call interface to couple the CORSICA non-linear plasma simulations to the controller environments developed within the Mathworks Matlab/Simulink environment. We present transport simulations using full shape and vertical stability control with evolution of the temperature profiles to provide simulations of the ITER controller and plasma response.