Closed-loop control of the safety factor profile in the TCV tokamak

J.E. Barton; E. Schuster; F. Felici; O. Sauter

doi:10.1109/CDC.2014.7040275

Closed-loop control of the safety factor profile in the TCV tokamak

J.E. Barton
, E. Schuster
, F. Felici
, O. Sauter

Control Systems Technology

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › Academic › peer-review

3 Citations (Scopus)

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.

Original language	English
Title of host publication	IEEE 53rd Annual Conference on Decision and Control (CDC 2014), 15-17 December 2014, Los Angeles, California, USA
Place of Publication	Piscataway
Publisher	Institute of Electrical and Electronics Engineers
Pages	5660-5665
Number of pages	6
ISBN (Electronic)	978-1-4673-6090-6
ISBN (Print)	978-1-4799-7746-8
DOIs	https://doi.org/10.1109/CDC.2014.7040275
Publication status	Published - 2014
Event	53rd IEEE Conference on Decision and Control, CDC 2014 - "J.W. Marriott Hotel", Los Angeles, United States Duration: 15 Dec 2014 → 17 Dec 2014 Conference number: 53 http://cdc2014.ieeecss.org/

Conference

Conference	53rd IEEE Conference on Decision and Control, CDC 2014
Abbreviated title	CDC
Country/Territory	United States
City	Los Angeles
Period	15/12/14 → 17/12/14
Internet address	http://cdc2014.ieeecss.org/

Access to Document

10.1109/CDC.2014.7040275

Cite this

@inproceedings{a1780999049a4d9ca1d854a5189379f3,

title = "Closed-loop control of the safety factor profile in the TCV tokamak",

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.",

author = "J.E. Barton and E. Schuster and F. Felici and O. Sauter",

year = "2014",

doi = "10.1109/CDC.2014.7040275",

language = "English",

isbn = "978-1-4799-7746-8",

pages = "5660--5665",

booktitle = "IEEE 53rd Annual Conference on Decision and Control (CDC 2014), 15-17 December 2014, Los Angeles, California, USA",

publisher = "Institute of Electrical and Electronics Engineers",

address = "United States",

note = "53rd IEEE Conference on Decision and Control, CDC 2014, CDC ; Conference date: 15-12-2014 Through 17-12-2014",

url = "http://cdc2014.ieeecss.org/",

}

Barton, JE, Schuster, E, Felici, F & Sauter, O 2014, Closed-loop control of the safety factor profile in the TCV tokamak. in IEEE 53rd Annual Conference on Decision and Control (CDC 2014), 15-17 December 2014, Los Angeles, California, USA. Institute of Electrical and Electronics Engineers, Piscataway, pp. 5660-5665, 53rd IEEE Conference on Decision and Control, CDC 2014, Los Angeles, California, United States, 15/12/14. https://doi.org/10.1109/CDC.2014.7040275

Closed-loop control of the safety factor profile in the TCV tokamak. / Barton, J.E.; Schuster, E.; Felici, F. et al.
IEEE 53rd Annual Conference on Decision and Control (CDC 2014), 15-17 December 2014, Los Angeles, California, USA. Piscataway: Institute of Electrical and Electronics Engineers, 2014. p. 5660-5665.

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › Academic › peer-review

TY - GEN

T1 - Closed-loop control of the safety factor profile in the TCV tokamak

AU - Barton, J.E.

AU - Schuster, E.

AU - Felici, F.

AU - Sauter, O.

N1 - Conference code: 53

PY - 2014

Y1 - 2014

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/84940943157

U2 - 10.1109/CDC.2014.7040275

DO - 10.1109/CDC.2014.7040275

M3 - Conference contribution

AN - SCOPUS:84940943157

SN - 978-1-4799-7746-8

SP - 5660

EP - 5665

BT - IEEE 53rd Annual Conference on Decision and Control (CDC 2014), 15-17 December 2014, Los Angeles, California, USA

PB - Institute of Electrical and Electronics Engineers

CY - Piscataway

T2 - 53rd IEEE Conference on Decision and Control, CDC 2014

Y2 - 15 December 2014 through 17 December 2014

ER -

Closed-loop control of the safety factor profile in the TCV tokamak

Abstract

Conference

Access to Document

Other files and links

Fingerprint

Cite this