Self-consistent quasi-linear modelling of Lower Hybrid Current Drive in ITER and DEMO

Joint Varenna-Lausanne International Workshop 2014

Cardinali, A.^1 ; Cesario, R.^1 ; Santini, F.^1 ; Amicucci, L.^1 ; Castaldo, C.^1 ; Ceccuzzi, S.^1 ; Panaccione, L.^1 ; Mirizzi, F.^1 ; Tuccillo, A.A.^1

ENEA, Unità Tecnica Fusione, Via E Fermi 45, Rome, Italy^1

关键词: Electron distribution function;    Lower hybrid current drive;    Magnetic configuration;    Plasma current profile;    Quasi-linear diffusion coefficients;    Ray-tracing equations;    Thermonuclear device;    Tokamak fusion reactors;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/561/1/012002/pdf
DOI  :  10.1088/1742-6596/561/1/012002

来源: IOP

【 摘 要 】

First pass absorption of the Lower Hybrid waves in thermonuclear devices like ITER and DEMO is modelled by coupling the ray tracing equations for the wave phase and amplitude with the quasi-linear evolution of the electron distribution function. A system of coupled ordinary differential equations for each Fourier component of the spectrum radiated by the LH antenna is derived and solved when considering both 1D/2D Fokker-Planck model for the electron distribution function. This allows to reconstruct and to evolve the quasi-linear diffusion coefficient consistently with the wave propagation, to calculate the power deposition profile and the amount of current driven by the wave. As usually assumed, the Lower Hybrid Current Drive is not effective in a plasma of a tokamak fusion reactor like ITER or DEMO, because the high electron temperature would enhance the wave absorption and then limit the RF power deposition to the very periphery of the plasma column (near the separatrix). In this work by extensively using this self-consistent modelling for the propagation and absorption of the LH wave, a parametric study on the wave spectrum (and consequently on the antenna design) as spectrum width, peak value, secondary lobes etc. has been performed very accurately. Such a careful investigation aims at controlling the power deposition layer possibly in the external half radius of the plasma, thus providing a valuable aid to the solution of how to control the plasma current profile in a toroidal magnetic configuration. This analysis is useful not only for exploring the possibility of profile control of a pulsed operation reactor, but also in order to reconsider the feasibility of steady state regime.