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  4. Actuator and diagnostic requirements of the ITER Plasma Control System
 
conference paper

Actuator and diagnostic requirements of the ITER Plasma Control System

Snipes, J. A.
•
Beltran, D.
•
Casper, T.
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2012
Fusion Engineering And Design
8th IAEA Technical Meeting on Control, Data Acquisition, and Remote Participation for Fusion Research

The ITER Plasma Control System (PCS) requires an extensive set of about 50 diagnostic systems to measure the plasma response and about 20 actuators to act on the plasma to carry out its control functions. The specifications and real limitations of the actuators and diagnostics are being assessed as part of the ongoing conceptual design of the PCS to understand the potential impact on plasma control. The actuators include magnetic coils (central solenoid (CS), poloidal field (PF), vertical stability (VS), edge localized mode (ELM), correction coils (CC)), heating and current drive (electron cyclotron (EC), ion cyclotron (IC), neutral beam injection (NBI), and possibly lower hybrid (LH)), glow discharge cleaning, fueling and impurity gas and pellet injection, vacuum pumping, and disruption mitigation systems. Diagnostic systems are prioritized according to their role in machine protection (MP), basic control (BC), advanced control (AC), and physics studies (PS). At the conceptual design phase, detailed control algorithms do not yet need to be specified, but conceptual solutions must be chosen that satisfy the PCS requirements for control within the real constraints of the diagnostics and actuators. The feasibility of the chosen solutions must be proven either through established control schemes on existing machines or through an R&D program to develop them before they will be required on ITER. The diagnostic and actuator requirements of the PCS will evolve from first plasma through the high performance DT phase. A comparison is made of the expected requirements to control vertical stability, sawteeth, neoclassical tearing modes (NTMs), edge localized modes (ELMs), error fields, resistive wall modes (RWMs), Alfven eigenmodes, and disruptions with the ITER baseline actuator and diagnostic specifications. (c) 2012 ITER Organization. Published by Elsevier B.V. All rights reserved.

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Type
conference paper
DOI
10.1016/j.fusengdes.2012.04.002
Web of Science ID

WOS:000314138900005

Author(s)
Snipes, J. A.
Beltran, D.
Casper, T.
Gribov, Y.
Isayama, A.
Lister, J.
Simrock, S.
Vayakis, G.
Winter, A.
Yang, Y.
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Date Issued

2012

Publisher

Elsevier Science Sa

Publisher place

Lausanne

Published in
Fusion Engineering And Design
Total of pages

7

Volume

87

Issue

12

Start page

1900

End page

1906

Subjects

Plasma control

•

ITER

•

Tokamak

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
CRPP  
SPC  
Event nameEvent placeEvent date
8th IAEA Technical Meeting on Control, Data Acquisition, and Remote Participation for Fusion Research

San Francisco, CA, USA

June 20-24, 2011

Available on Infoscience
March 28, 2013
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/91140
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