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Title: EC power management in ITER for NTM control: the path from the commissioning phase to demonstration discharges

Journal Article · · EPJ Web of Conferences
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  1. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  2. ITER Organization, St. Paul Les Durance (France)
  3. Istituto di Fisica del Plasma, Milano (Italy)
  4. Max-Planck-Institute fur Plasmaphysiks, Garching (Germany)

Time dependent simulations that evolve consistently the magnetic equilibrium and plasma pressure profiles and the width and frequency rotation of magnetic islands under the effect of the Electron Cyclotron feedback system are used to assess whether the control of NTMs on ITER is compatible with other simulataneous functionalities of the EC system, like core heating and current profile tailoring, or sawtooth control. Furthermore, results indicate that the power needs for control can be reduced if the EC power is reserved and if pre-emptive control is used as opposed to an active search for an already developed island.

Research Organization:
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
AC02-09CH11466
OSTI ID:
1411213
Journal Information:
EPJ Web of Conferences, Vol. 157; Conference: Radio Frequency Power in Plasmas, Aix-en Provence (France), 30 May - 2 Jun 2017; ISSN 2100-014X
Publisher:
EDP SciencesCopyright Statement
Country of Publication:
United States
Language:
English

References (12)

Nonlinear evolution of double tearing modes in tokamaks journal January 2000
Optimization of the ITER electron cyclotron equatorial launcher for improved heating and current drive functional capabilities journal June 2014
Requirements on localized current drive for the suppression of neoclassical tearing modes journal August 2011
Integrated modelling of island growth, stabilization and mode locking: consequences for NTM control on ITER journal August 2012
Potential of the ITER electron cyclotron equatorial launcher for heating and current drive at nominal and reduced fields journal February 2012
TORBEAM, a beam tracing code for electron-cyclotron waves in tokamak plasmas journal May 2001
On recent results in the modelling of neoclassical-tearing-mode stabilization via electron cyclotron current drive and their impact on the design of the upper EC launcher for ITER journal January 2015
Neoclassical tearing modes in Tokamak Fusion Test Reactor experiments. I. Measurements of magnetic islands and Δ journal April 1998
Requirements for alignment of electron cyclotron current drive for neoclassical tearing mode stabilization in ITER journal April 2008
Evaluating neoclassical tearing mode detection with ECE for control on ITER journal December 2012
The targeted heating and current drive applications for the ITER electron cyclotron system journal February 2015
Actuator and diagnostic requirements of the ITER Plasma Control System journal December 2012

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