[en] This administrative plan establishes the framework, organization, and methods for integrating a number of diverse system requirements. Essential to the integration process is the establishment of concise communication between program participants. Single point contacts have been designated at GA, DOE/OFE, and DOE/SAN so that all official correspondence is routed through one individual at each management control point. The names of the individuals are given

[en] OAK-B135 The physics model of electron cyclotron heating (ECH) and current drive (ECCD) is becoming well validated through systematic comparisons of theory and experiment. This work has shown that ECH and ECCD can be highly localized and robustly controlled in toroidal plasma confinement systems, leading to applications including stabilization of magnetohydrodynamic (MHD) instabilities like neoclassical tearing modes, control and sustainment of desired profiles of current density and plasma pressure, and studies of localized transport in laboratory plasmas. The experimental work was supported by a broad base of theory based on first principles which is now well encapsulated in linear ray tracing codes describing wave propagation, absorption, and current drive and in fully relativistic quasilinear Fokker-Planck codes describing in detail the response of the electrons to the energy transferred from the wave. The subtle balance between wave-induced diffusion and Coulomb relaxation in velocity space provides an understanding of the effects of trapping of current-carrying electrons in the magnetic well. Strong quasilinear effects and radial transport of electrons, which may broaden the driven current profile, have also been observed under some conditions and appear to be consistent with theory, but in large devices these are usually insignificant. The agreement of theory and experiment, the wide range of established applications, and the technical advantages of ECH support the application of ECH in next-step tokamaks and stellarators

No abstract available

[en] A review of electron cyclotron heating (ECH) experiments in tokamaks and stellarators is presented. ECH has the desirable properties of easily controlled, highly localized absorption, insensitivity to plasma boundary conditions, and high power density. The behavior of electron cyclotron waves is described by well developed theory, and experimenal determinations of absorption and propagation tend to support the theory. Global energy confinement scalings suggest that the confinement deterioration with increasing auxiliary power found with other heating methods is also found with ECH, with some exceptions. The application of ECH to the generation of plasmas with high poloidal beta, control of MHD activity, noninductive plasma current drive, and measurement of local electron thermal conductivity is discussed. 55 refs

[en] In electron cyclotron heating (ECH) experiments on the Doublet III tokamak, operated in the expanded boundary divertor configuration, a correlation is found between plasma corotation prior to ECH and high efficiency of plasma heating during ECH. Enhanced particle transport is associated with poor heating efficiency in nonrotating discharges

[en] This report is intended to very briefly assess the status of research into electron cyclotron heating (ECH) and current drive, and to summarize the need for ECH in the compact ignition tokamak (CIT) and engineering tokamak reactor (ETR) devices. It is clear that ECH and current drive experiments need to be performed in the power range between that of present experiments and the power level required for next generation devices. In addition, the DIII-D program of confinement improvement in high beta plasmas can be furthered by the availability of an ECH source compatible in power level with the neutral beam injectors. This report concludes with a discussion of what could be accomplished on DIII-D with a 6 MW ECH source at 120 GHz and how this source might be implemented

[en] Electron cyclotron heating experiments are described in which 28 GHz microwave power is injected into the JFT-2 tokamak. Ordinary mode power injected from the low field side increased the central electron temperature from 600 eV to 1000 eV with 110 kW, for densities below the ordinary mode cutoff density of 1.0 x 10¹³ cm^-3. Extraordinary mode power launched obliquely from the high field side increased the temperature from 600 eV to 1200 eV with 85 kW, for densities well below the extraordinary mode cutoff density, and effective heating was maintained close to the cutoff density of 1.6 x 10¹³ cm^-3. The extraordinary mode launched obliquely was also found to heat more efficiently and to a higher density than the extraordinary wave launched perpendicularly. On this basis, the Doublet III ECH experiments which will use up to 2 MW of 60 GHz power are designed to make use of oblique inside launch of a pure extraordinary mode. The waveguide transmission system to accomplish this is discussed

[en] In order to improve the noise immunity and increase the availability of the DIII-D ECE radiometer, the radiometer receiver will be located outside the radiation shield wall. Further noise immunity is obtained by the use of a 50 kHz rf modulator, which is compatible with the 90 to 140 GHz low loss, single mode transmission system, the design and expected performance of which will be discussed. The testing of microwave components and the absolute calibration of the system is also discussed

[en] The transmission and launching scheme being used for the ECH experiments at 60 GHz on Doublet III and its operation at high power is described. The system uses the TE⁰¹ to TE¹¹ mode converter at the antenna. The system provides an acceptable load to the gyrotron, rarely arcs, and maintains good mode purity

[en] Electron-cyclotron-heating experiments have been carried out on the Doublet III tokamak. Two 60-GHz gyrotrons were used to generate about 255 kW of power delivered to the plasma in the ordinary-mode polarization. The antenna launches a 16₀ FWHM beam from the large major radius side (outside) of the plasma at a beam center angle of 12₀ from a major radius. Pulses up to 85 msec long were applied, with the fundamental resonance (21.4 kG) near the plasma center. Plasma current was 300 to 350 kA, and the configuration was mostly expanded boundary with an elongation of 1.4 to 1.6 and density of 2 to 3 x 10₁₃ cm^-₃. Electron-temperature increases up to 1 keV at the plasma center due to ECH are found by Thomson scattering and electron-cyclotron radiation at the second harmonic. Soft x-ray analysis also shows central electron heating and profile broadening when the resonance is moved outside of the plasma center