Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Robust control of the current profile and plasma energy in EAST

Journal Article · · Fusion Engineering and Design
 [1];  [2]
  1. Lehigh Univ., Bethlehem, PA (United States); DOE/OSTI
  2. Lehigh Univ., Bethlehem, PA (United States)
Integrated control of the toroidal current density profile, or alternatively the q-profile, and plasma stored energy is essential to achieve advanced plasma scenarios characterized by high plasma confinement, magnetohydrodynamics stability, and noninductively driven plasma current. The q-profile evolution is closely related to the evolution of the poloidal magnetic flux profile, whose dynamics is modeled by a nonlinear partial differential equation (PDE) referred to as the magnetic-flux diffusion equation (MDE). The MDE prediction depends heavily on the chosen models for the electron temperature, plasma resistivity, and non-inductive current drives. To aid control synthesis, control-oriented models for these plasma quantities are necessary to make the problem tractable. However, a relatively large deviation between the predictions by these control-oriented models and experimental data is not uncommon. For this reason, the electron temperature, plasma resistivity, and non-inductive current drives are modeled for control synthesis in this work as the product of an “uncertain” reference profile and a nonlinear function of the different auxiliary heating and current-drive (H&CD) source powers and the total plasma current. The uncertainties are quantified in such a way that the family of models arising from the modeling process is able to capture the q-profile and plasma stored energy dynamics from a typical EAST shot. A control-oriented nonlinear PDE model is developed by combining the MDE with the “uncertain” models for the electron temperature, plasma resistivity, and non-inductive current drives. This model is then rewritten into a control framework to design a controller that is robust against the modeled uncertainties. The resulting controller utilizes EAST's H&CD powers and total plasma current to regulate the q profile and plasma stored energy even when mismatches between modeled and actual dynamics are present. The effectiveness of the controller is demonstrated through nonlinear simulations.
Research Organization:
Lehigh Univ., Bethlehem, PA (United States)
Sponsoring Organization:
USDOE; USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
SC0010537
OSTI ID:
1611441
Alternate ID(s):
OSTI ID: 1557895
Journal Information:
Fusion Engineering and Design, Journal Name: Fusion Engineering and Design Journal Issue: A Vol. 146; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (7)

Receding-horizon optimal control of the current profile evolution during the ramp-up phase of a tokamak discharge journal January 2011
Towards model-based current profile control at DIII-D journal October 2007
Neoclassical conductivity and bootstrap current formulas for general axisymmetric equilibria and arbitrary collisionality regime journal July 1999
Toroidal current profile control during low confinement mode plasma discharges in DIII-D via first-principles-driven model-based robust control synthesis journal November 2012
Control of the tokamak safety factor profile with time-varying constraints using MPC journal January 2015
Physics-based control-oriented modeling and robust feedback control of the plasma safety factor profile and stored energy dynamics in ITER journal September 2015
Backstepping Control of the Toroidal Plasma Current Profile in the DIII-D Tokamak journal September 2014

Similar Records

Physics-based control-oriented modeling of the current density profile evolution in NSTX-Upgrade
Journal Article · Wed May 10 20:00:00 EDT 2017 · Fusion Engineering and Design · OSTI ID:1465372

Determination of the noninductive current profile in tokamak plasmas
Journal Article · Sun Oct 30 23:00:00 EST 1994 · Physical Review Letters; (United States) · OSTI ID:6946474

Neural network model of neutral beam injection in the EAST tokamak to enable fast transport simulations
Journal Article · Sun Feb 12 19:00:00 EST 2023 · Fusion Engineering and Design · OSTI ID:1974424