DocumentCode :
115990
Title :
Closed-loop control of the safety factor profile in the TCV tokamak
Author :
Barton, Justin E. ; Schuster, Eugenio ; Felici, Federico ; Sauter, Olivier
Author_Institution :
Dept. of Mech. Eng. & Mech., Lehigh Univ., Bethlehem, PA, USA
fYear :
2014
fDate :
15-17 Dec. 2014
Firstpage :
5660
Lastpage :
5665
Abstract :
A key property that has a close relationship to both the performance and stability of the plasma in nuclear fusion tokamak devices is the safety factor profile (q-profile). As a result, extensive research has been conducted to develop algorithms to actively control the q-profile evolution with the goal of optimizing the tokamak approach to fusion energy production. The actuators that can be used to control the q-profile are the total plasma current, the auxiliary heating/current-drive system and the line-average electron density. In this work, we first investigate the effect that pure plasma auxiliary heating has on the q-profile in low performance (L-mode) operating scenarios in the TCV tokamak. This study indicates that pure auxiliary heating has a small effect on the q-profile in the examined scenarios. Therefore, feedback controllers that utilize the total plasma current and exclusively the auxiliary current-drive capabilities are designed for q-profile control in TCV. The controllers are designed to put emphasis on achieving the target q-profile in different spatial regions and to respond differently to errors in the q-profile. The control performance of each controller is tested with the simplified physics-based plasma profile simulation code RAPTOR. The comparison of the closed-loop performance of these controllers is done in preparation for future q-profile control experiments in the TCV tokamak.
Keywords :
Tokamak devices; closed loop systems; feedback; fusion reactor safety; physical instrumentation control; plasma heating; L-mode operating scenarios; RAPTOR; TCV tokamak; auxiliary current-drive capabilities; closed-loop control; feedback controllers; low performance operating scenarios; physics-based plasma profile simulation code; pure plasma auxiliary heating; q-profile control; safety factor profile; total plasma current; Current density; Heating; Mathematical model; Plasma temperature; Tokamaks; Toroidal magnetic fields;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Decision and Control (CDC), 2014 IEEE 53rd Annual Conference on
Conference_Location :
Los Angeles, CA
Print_ISBN :
978-1-4799-7746-8
Type :
conf
DOI :
10.1109/CDC.2014.7040275
Filename :
7040275
Link To Document :
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