EPJ Web Conf.
Volume 157, 201722 Topical Conference on Radio-Frequency Power in Plasmas
|Number of page(s)||10|
|Published online||23 October 2017|
Current Challenges in the First Principle Quantitative Modelling of the Lower Hybrid Current Drive in Tokamaks
1 CEA, IRFM, F-13108, Saint-Paul-lez-Durance, France
2 PSFC, MIT, MA-02139, Cambridge, USA
3 General Atomics, CA-92186-5606, San Diego, USA
4 ASIPP, 230031, Hefei, China
5 EPFL, CRPP, F-13108, Lausanne
Published online: 23 October 2017
The Lower Hybrid (LH) wave is widely used in existing tokamaks for tailoring current density profile or extending pulse duration to steady-state regimes. Its high efficiency makes it particularly attractive for a fusion reactor, leading to consider it for this purpose in ITER tokamak. Nevertheless, if basics of the LH wave in tokamak plasma are well known, quantitative modeling of experimental observations based on first principles remains a highly challenging exercise, despite considerable numerical efforts achieved so far. In this context, a rigorous methodology must be carried out in the simulations to identify the minimum number of physical mechanisms that must be considered to reproduce experimental shot to shot observations and also scalings (density, power spectrum). Based on recent simulations carried out for EAST, Alcator C-Mod and Tore Supra tokamaks, the state of the art in LH modeling is reviewed. The capability of fast electron bremsstrahlung, internal inductance li and LH driven current at zero loop voltage to constrain all together LH simulations is discussed, as well as the needs of further improvements (diagnostics, codes, LH model), for robust interpretative and predictive simulations.
© The authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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