Feedback Control Design for Noninductively Sustained Scenarios in NSTX-U Using TRANSP
- 1. Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ 08540 (United States)
Description
Full text: Spherical torus based designs for fusion nuclear science facilities and pilot plants have little to no room for a central solenoid, and require the plasma current to be generated noninductively. Recently completed upgrades to NSTX-U will enable the study of noninductive scenarios, including start-up, ramp-up, and flattop current sustainment. This paper examines active control of such scenarios using TRANSP simulations. TRANSP is a time-dependent integrated modelling code for prediction and interpretive analysis of tokamak experimental data. Its predictive mode has been used for scenario development on NSTX-U, including fully noninductive scenarios, and exploration of approaches to noninductive ramp-up. Recently, the ability to include feedback control algorithms in TRANSP has been developed. The actuators considered for control in this work are the six neutral beam sources and the plasma boundary shape. The neutral beam sources allow the current drive deposition and heating to be tailored in real-time. The primary plasma boundary shape parameter that is considered is the midplane outer gap. Increasing this gap leads to increased bootstrap current and moves the neutral beam deposition off axis, tending to increase the central safety factor. To understand the response of the plasma current, stored energy, and central safety factor to these actuators and to enable systematic design of control algorithms, simulations were run in which the actuators were modulated and a linearized dynamic response model was generated. The simplified model was used to design several PID control laws using different combinations of actuators and measurements. Closed loop simulations show that modest changes in the outer gap and heating power can improve the response time of the system, reject perturbations, and track target values of the controlled values. Strong coupling between the controlled quantities is observed, making multivariable control design an important next step. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 287
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49089456
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BOOTSTRAP CURRENT; COMPUTERIZED SIMULATION; EXPERIMENTAL DATA; HEATING; NEUTRAL BEAM SOURCES; NSTX DEVICE; PILOT PLANTS; PLASMA; SAFETY; SOLENOIDS; SPHERICAL CONFIGURATION; START-UP; STORED ENERGY; STRONG-COUPLING MODEL; THERMONUCLEAR REACTIONS; TIME DEPENDENCE
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFIGURATION; CURRENTS; DATA; ELECTRIC COILS; ELECTRIC CURRENTS; ELECTRICAL EQUIPMENT; ENERGY; EQUIPMENT; FUNCTIONAL MODELS; INFORMATION; MATHEMATICAL MODELS; NUCLEAR REACTIONS; NUCLEOSYNTHESIS; NUMERICAL DATA; PARTICLE MODELS; PHYSICAL PROPERTIES; SIMULATION; SPHEROMAK DEVICES; SYNTHESIS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES
Optional Information
- Contract/Grant/Project number
- Contract DE-AC02-09CH11466
- Notes
- Abstract only; 5 refs.
- Secondary number(s)
- IAEA-CN--234-0371