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Title: The targeted heating and current drive applications for the ITER electron cyclotron system

Journal Article · · Physics of Plasmas
DOI:https://doi.org/10.1063/1.4908598· OSTI ID:22408053
; ; ; ; ; ;  [1]; ;  [2]; ;  [3];  [4];  [5];  [6]
  1. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)
  2. Fusion for Energy, Josep Pla 2, Barcelona 08019 (Spain)
  3. Istituto di Fisica del Plasma CNR, 20125 Milano (Italy)
  4. US ITER Project Office, ORNL, 1055 Commerce Park, PO Box 2008, Oak Ridge, Tennessee 37831 (United States)
  5. Max-Planck-Institut für Plasmaphysik, D-85748 Garching (Germany)
  6. Japan Atomic Energy Agency (JAEA), Naka, Ibaraki 311-0193 (Japan)

A 24 MW Electron Cyclotron (EC) system operating at 170 GHz and 3600 s pulse length is to be installed on ITER. The EC plant shall deliver 20 MW of this power to the plasma for Heating and Current Drive (H and CD) applications. The EC system is designed for plasma initiation, central heating, current drive, current profile tailoring, and Magneto-hydrodynamic control (in particular, sawteeth and Neo-classical Tearing Mode) in the flat-top phase of the plasma. A preliminary design review was performed in 2012, which identified a need for extended application of the EC system to the plasma ramp-up, flattop, and ramp down phases of ITER plasma pulse. The various functionalities are prioritized based on those applications, which can be uniquely addressed with the EC system in contrast to other H and CD systems. An initial attempt has been developed at prioritizing the allocated H and CD applications for the three scenarios envisioned: ELMy H-mode (15 MA), Hybrid (∼12 MA), and Advanced (∼9 MA) scenarios. This leads to the finalization of the design requirements for the EC sub-systems.

OSTI ID:
22408053
Journal Information:
Physics of Plasmas, Vol. 22, Issue 2; Other Information: (c) 2015 EURATOM; Country of input: International Atomic Energy Agency (IAEA); ISSN 1070-664X
Country of Publication:
United States
Language:
English

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Integrated Tokamak modeling: When physics informs engineering and research planning journal May 2018
Modeling the electron cyclotron emission below the fundamental resonance in ITER journal July 2019
Heating neutral beams for ITER: negative ion sources to tune fusion plasmas journal May 2017
Survey of heating and current drive for K-DEMO journal January 2018
The time-dependent simulation of CFETR baseline steady-state scenarios journal July 2018
Real-time plasma state monitoring and supervisory control on TCV journal January 2019
Control of neoclassical tearing modes and integrated multi-actuator plasma control on TCV journal June 2019
Inference of α -particle density profiles from ITER collective Thomson scattering journal August 2019
Non-linear simulations of neoclassical tearing mode control by externally driven RF current and heating, with application to ITER journal August 2019
Real-time plasma state monitoring and supervisory control on TCV text January 2019