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Title: Overview of the preliminary design of the ITER plasma control system

Journal Article · · Nuclear Fusion
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  1. ITER Organization, St. Paul Lez Durance (France)
  2. Consorzio CREATE, Napoli (Italy)
  3. D. V. Efremov Inst. of Electrophysical Apparatus, St. Petersburg (Russian Federation)
  4. Eindhoven Univ. of Technology (Netherlands)
  5. CEA, IRFM, St. Paul Lez Durance (France)
  6. Central Atomics, San Diego, CA (United States)
  7. Culham Science Centre, Abingdon (United Kingdom). Culham Centre for Fusion Energy (CCFE), EURATOM/UKAEA Fusion Association
  8. National Research Centre (NRC), Moscow (Russian Federation). Kurchatov Inst. (NRCKI)
  9. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  10. Max Planck Inst. fur Plasmaphysik, Garching (Germany)

An overview of the Preliminary Design of the ITER Plasma Control System (PCS) is described here, which focusses on the needs for 1st plasma and early plasma operation in hydrogen/helium (H/He) up to a plasma current of 15 MA with moderate auxiliary heating power in low confinement mode (L-mode). Candidate control schemes for basic magnetic control, including divertor operation and kinetic control of the electron density with gas puffing and pellet injection, were developed. Commissioning of the auxiliary heating systems is included as well as support functions for stray field topology and real-time plasma boundary reconstruction. Initial exception handling schemes for faults of essential plant systems and for disruption protection were developed. The PCS architecture was also developed to be capable of handling basic control for early commissioning and the advanced control functions that will be needed for future high performance operation. A plasma control simulator is also being developed to test and validate control schemes. To handle the complexity of the ITER PCS, a systems engineering approach has been adopted with the development of a plasma control database to keep track of all control requirements.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC02-09-CH11466
OSTI ID:
1434642
Journal Information:
Nuclear Fusion, Vol. 57, Issue 12; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 21 works
Citation information provided by
Web of Science

References (26)

Physics of the conceptual design of the ITER plasma control system journal May 2014
Towards the conceptual design of the ITER real-time plasma control system journal March 2014
Novel aspects of plasma control in ITER journal February 2015
The ITER Plasma Control System Simulation Platform journal October 2015
Transient electromagnetic analysis in tokamaks using typhoon code journal June 1996
Studies of Plasma Equilibrium and Transport in a Tokamak Fusion Device with the Inverse-Variable Technique journal December 1993
Characterisation of plasma breakdown at JET with a carbon and ITER-like wall journal April 2013
Plasma vertical stabilisation in ITER journal June 2015
Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping journal February 2015
Validation of a new mixed Bohm/gyro-Bohm model for electron and ion heat transport against the ITER, Tore Supra and START database discharges journal July 1998
Experimental vertical stability studies for ITER performance and design guidance journal September 2009
Large amplitude quasi-stationary MHD modes in JET journal June 1988
Real time equilibrium reconstruction for tokamak discharge control journal July 1998
Tokamak equilibrium reconstruction code LIUQE and its real time implementation journal February 2015
Iterative Axisymmetric Identification Algorithm (IAIA) for real-time reconstruction of the plasma boundary of ITER journal October 2013
Improved Three-Dimensional CCS Method Analysis for the Reconstruction of the Peripheral Magnetic Field Structure in a Finite Beta Helical Plasma journal January 2013
Event detection and exception handling strategies in the ASDEX Upgrade discharge control system journal October 2013
From the conceptual design to the first simulation of the new WEST plasma control system journal October 2015
Towards a preliminary design of the ITER plasma control system architecture journal February 2017
Disruptions in ITER and strategies for their control and mitigation journal August 2015
Scaling of the MHD perturbation amplitude required to trigger a disruption and predictions for ITER journal December 2015
An advanced disruption predictor for JET tested in a simulated real-time environment journal January 2010
Robustness and increased time resolution of JET Advanced Predictor of Disruptions journal October 2014
Design and first applications of the ITER integrated modelling & analysis suite journal October 2015
Non-linear model-based optimization of actuator trajectories for tokamak plasma profile control journal January 2012
The CRONOS suite of codes for integrated tokamak modelling journal March 2010

Cited By (4)

Summary of the FESAC Transformative Enabling Capabilities Panel Report journal March 2019
Metis: a fast integrated tokamak modelling tool for scenario design journal August 2018
Real-time plasma state monitoring and supervisory control on TCV journal January 2019
Real-time plasma state monitoring and supervisory control on TCV text January 2019

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