TY - JOUR
T1 - Current Challenges in the First Principle Quantitative Modelling of the Lower Hybrid Current Drive in Tokamaks
AU - Peysson, Y.
AU - Bonoli, P. T.
AU - Chen, J.
AU - Garofalo, A.
AU - Hillairet, J.
AU - Li, M.
AU - Qian, J.
AU - Shiraiwa, S.
AU - Decker, J.
AU - Ding, B. J.
AU - Ekedahl, A.
AU - Goniche, M.
AU - Zhai, X.
N1 - Publisher Copyright:
© 2017 The authors, published by EDP Sciences.
PY - 2017/10/23
Y1 - 2017/10/23
N2 - 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.
AB - 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.
UR - https://www.scopus.com/pages/publications/85032642710
UR - https://www.scopus.com/inward/citedby.url?scp=85032642710&partnerID=8YFLogxK
U2 - 10.1051/epjconf/201715702007
DO - 10.1051/epjconf/201715702007
M3 - Conference article
AN - SCOPUS:85032642710
SN - 2101-6275
VL - 157
JO - EPJ Web of Conferences
JF - EPJ Web of Conferences
M1 - 02007
T2 - 22nd Topical Conference on Radio-Frequency Power in Plasmas 2017
Y2 - 30 May 2017 through 2 June 2017
ER -