Study of lower hybrid current drive efficiency over a wide range of FTU plasma parameters
نویسندگان
چکیده
The key quantities affecting the efficiency of Lower Hybrid (LH) radiofrequency waves in driving non-inductively the toroidal current in a tokamak have been recognized by means of a linear regression analysis over all the data available for the Frascati Tokamak Upgrade. The parameter space is bounded within the following ranges: line averaged plasma density 0.29 × 1020 n̄e 1.29 × 1020 m−3, central electron temperatures 1.1 Te0 7.4 keV, corresponding to volume averaged temperatures 0.27 〈Te〉 1.2 keV, plasma current 0.3 Ip 0.7 MA, magnetic field 4 BT0 7.2 T, with a safety factor between 4.7 qa 10.7, LH power 0.4 PLH 2.1 MW and LH parallel refraction index 1.32 N‖0 2.42. The experimental current drive (CD) efficiency, reduced to the effective ion charge state Zeff = 1, varies for this data set within 0.12 η∗ CD 0.34 A W−1 × 1020 m−2. A linear regression analysis gives a reliable scaling law for η∗ CD with a correlation coefficient close to 0.9 that points out the importance of the various quantities. The CD efficiency is a significantly increasing function of 〈Te〉 and BT, and a decreasing one of qa and PLH, while N‖ and n̄e have limited influence. The physical reasons for the observed trend related to the variation of each parameter are recognized and discussed. The main causes are identified in the modification suffered by the N‖ spectrum along the ray trajectory before the power can be absorbed by the electrons and in the interaction with the edge plasma density fluctuations. The analysis also allows putting into evidence the synergy between the LH and electron cyclotron waves, when the latter are absorbed directly on the LH generated suprathermal electron tails and produce the highest values of η∗ CD. PACS numbers: 52.55.Wq, 52.50.Sw (Some figures in this article are in colour only in the electronic version)
منابع مشابه
Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks
Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy. The spherical tours (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as NSTX and higher toroidal beta regimes and improves the design of a po...
متن کاملAnalysis of the Chaotic Behavior of the Lower Hybrid Wave Propagation in Magnetised Plasma by Hamiltonian Theory
The Hamiltonian character of the ray tracing equations describing the propagation of the Lower Hybrid Wave (LHW) in a magnetic confined plasma device (tokamak) is investigated in order to study the evolution of the parallel wave number along the propagation path. The chaotic diffusion of the “time-averaged” parallel wave number at higher values (with respect to that launched by the antenna at t...
متن کاملCurrent drive at plasma densities required for thermonuclear reactors.
Progress in thermonuclear fusion energy research based on deuterium plasmas magnetically confined in toroidal tokamak devices requires the development of efficient current drive methods. Previous experiments have shown that plasma current can be driven effectively by externally launched radio frequency power coupled to lower hybrid plasma waves. However, at the high plasma densities required fo...
متن کاملA Modified Phase-Shifted Pulse Width Modulation to Extend Linear Operation of Hybrid Modular Multi-level Converter
Recently, hybrid modular multi-level converters, which are configured as full and half bridge sub-modules, are developed and utilized in the wide area of applications. Compared to its non-hybrid counterpart, these converters have several advantages such as the ability to nullify the DC side fault current and controlling AC side reactive power during the faults. This paper proposes a modified ph...
متن کاملOV / 4 - 2 1 Overview of the FTU Results
New FTU ohmic discharges with Liquid Lithium Limiter at IP = 0.7-0.75 MA, BT =7 T, ne0 ≥ 510m, confirm the spontaneous transition to an enhanced confinement regime, 1.3-1.4 times ITER-97-L, when the density peaking factor is above a threshold value of 1.7-1.8. The improved confinement derives from a reduction of electron thermal conductivity (χe) as density increases, while ion thermal conducti...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
عنوان ژورنال:
دوره شماره
صفحات -
تاریخ انتشار 2005