Progress and improvement of KSTAR plasma control using model-based control simulators
Creators
- 1. National Fusion Research Institute, 169-148 Gwahak-ro, yuseong-gu, Daejeon (Korea, Republic of)
- 2. General Atomics, San Diego, CA (United States)
- 3. Princeton Plasma Physics Laboratory, Princeton, NJ (United States)
- 4. University of Science and Technology, Daejeon (Korea, Republic of)
Description
Superconducting tokamaks like KSTAR, EAST and ITER need elaborate magnetic controls mainly due to either the demanding experiment schedule or tighter hardware limitations caused by the superconducting coils. In order to reduce the operation runtime requirements, two types of plasma simulators for the KSTAR plasma control system (PCS) have been developed for improving axisymmetric magnetic controls. The first one is an open-loop type, which can reproduce the control done in an old shot by loading the corresponding diagnostics data and PCS setup. The other one, a closed-loop simulator based on a linear nonrigid plasma model, is designed to simulate dynamic responses of the plasma equilibrium and plasma current (Ip) due to changes of the axisymmetric poloidal field (PF) coil currents, poloidal beta, and internal inductance. The closed-loop simulator is the one that actually can test and enable alteration of the feedback control setup for the next shot. The simulators have been used routinely in 2012 plasma campaign, and the experimental performances of the axisymmetric shape control algorithm are enhanced. Quality of the real-time EFIT has been enhanced by utilizations of the open-loop type. Using the closed-loop type, the decoupling scheme of the plasma current control and axisymmetric shape controls are verified through both the simulations and experiments. By combining with the relay feedback tuning algorithm, the improved controls helped to maintain the shape suitable for longer H-mode (10–16 s) with the number of required commissioning shots largely reduced
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2013.12.040Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2013.12.040;
- PII
- S0920-3796(13)00754-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 89
- Journal Issue
- 5
- Journal Page Range
- p. 542-547
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 9. IAEA technical meeting on control, data acquisition, and remote participation for fusion research
- Dates
- 6-10 May 2013
- Place
- Hefei (China)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46090460
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; AXIAL SYMMETRY; COMPUTERIZED SIMULATION; CONTROL SYSTEMS; DECOUPLING; ELECTRIC CURRENTS; H-MODE PLASMA CONFINEMENT; INDUCTANCE; ITER TOKAMAK; PLASMA; PLASMA DIAGNOSTICS; PLASMA SIMULATION; SIMULATORS; SUPERCONDUCTING MAGNETS
- Descriptors DEC
- ANALOG SYSTEMS; CLOSED PLASMA DEVICES; CONFINEMENT; CURRENTS; ELECTRICAL EQUIPMENT; ELECTRICAL PROPERTIES; ELECTROMAGNETS; EQUIPMENT; FUNCTIONAL MODELS; MAGNETIC CONFINEMENT; MAGNETS; MATHEMATICAL LOGIC; PHYSICAL PROPERTIES; PLASMA CONFINEMENT; SIMULATION; SUPERCONDUCTING DEVICES; SYMMETRY; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.