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Please use this identifier to cite or link to this item: http://arks.princeton.edu/ark:/88435/dsp01pc289m87q
Title: TRANSP-based Optimization Towards Tokamak Scenario Development
Contributors: W.P. Wehner, E. Schuster, M.D. Boyer, F. Poli
U. S. Department of Energy
Keywords: TRANSP
scenario development
optimal control design
optimal plasma scenario planning
NSTX-U
DIII-D
Issue Date: Apr-2019
Publisher: Princeton Plasma Physics Laboratory, Princeton University
Related Publication: Fusion Engineering and Design
Abstract: An optimization approach that incorporates the predictive transport code TRANSP is proposed for tokamak scenario development. Optimization methods are often employed to develop open-loop control strategies to aid access to high performance tokamak scenarios. In general, the optimization approaches use control-oriented models, i.e. models that are reduced in complexity and prediction accuracy as compared to physics-oriented transport codes such as TRANSP. In the presented approach, an optimization procedure using the TRANSP code to simulate the tokamak plasma is considered for improved predictive capabilities. As a test case, the neutral beam injection (NBI) power is optimized to develop a control strategy that maximizes the non-inductive current fraction during the ramp-up phase for NSTX-U. Simulation studies towards the achievement of non-inductive ramp up in NSTX-U have already been carried out with the TRANSP code. The optimization-based approach proposed in this work is used to maximize the non-inductive current fraction during ramp-up in NSTX-U, demonstrating that the scenario development task can be automated. An additional test case considers optimization of the current ramp rate in DIII-D for obtaining a stationary plasma characterized by a flat loop voltage profile in the flattop phase.
URI: http://arks.princeton.edu/ark:/88435/dsp01pc289m87q
Appears in Collections:NSTX-U

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