Published May 3, 2018 | Version v1
Report

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)

Part of:
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material

Additional details

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)

Optional Information

Contract/Grant/Project number
Contract DE-AC02-09CH11466
Notes
Abstract only; 5 refs.
Secondary number(s)
IAEA-CN--234-0371