[en] This paper will consist of four parts. First, I will describe the basic EBT machine and its operation. Second, I will discuss the experimental results obtained on the present machine and how they relate to neoclassical transport theory. This will include a discussion of the chronology of the estimates of the confinement time and why they have changed. Third, I will briefly discuss some preliminary proposals on how to improve the confinement and operation of EBTs, and fourth, I will review some of the potential advantages of EBTs as fusion reactors and the calculations indicating the critical issues

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[en] Two methods of tuning and matching the ion cyclotron heating (ICH) antennas for the Burning Plasma Experiment (BPX) to the BPX plasma have been analyzed. Both appear to provide adequate tuning and matching capabilities. However, there are trade-offs between the frequency range that can be covered and the compactness of the high-voltage region of the transmission lines that makes up of the matching network. 4 refs., 5 figs

[en] FIRE (Fusion Ignition Research Experiment) is a high-field, burning-plasma tokamak that is being studied as a possible option for future fusion research. Preliminary parameters for this machine are R₀ approximately equal to 2 m, a approximately equal to 0.5 m, B₀ approximately equal to 10 T, and I_p approximately equal to 6 MA. Magnetic field coils are to be made of copper and precooled with LN₂ before each shot. The flat-top pulse length desired is greater than or equal to 10s. Ion cyclotron and lower hybrid rf systems will be used for heating and current drive. Present specifications call for 30 MW of ion cyclotron heating power, with 25 MW of lower hybrid power as an upgrade option

[en] Ion cyclotron heating (ICH) has been chosen as the primary method for providing auxiliary heating power to the plasma in the Compact Ignition Tokamak (CIT). Sustained progress in ion cyclotron range of frequencies (ICRF) heating experiments, together with supporting technology development, continues to justify selection of this technique as the preferred one for heating CIT to ignition. However, the CIT requirements are sufficiently different from existing achievements that continued experimentation and development are needed to meet the goals of the CIT experiment with a high degree of reliability. The purpose of this report is fourfold: (1) to review briefly the physics and technology research and development (R and D) needs for ICH on CIT, (2) to review the status of and planned programs for ICH on US and international machines, (3) to propose a unified ''mainline'' R and D program specifically geared to testing components for CIT, and (4) to assess the needs for experiments including C-Mod, the Tokamak Fusion Test Reactor (TFTR), and DIII-D to provide earlier information and improved probability of success for CIT ICH. 4 refs., 4 figs., 5 tabs

[en] This report describes the analysis and optimization of the proposed International Thermonuclear Experimental Reactor (ITER) Antenna Array for the ion cyclotron range of frequencies (ICRF). The objectives of this effort were to: (1) minimize the applied radiofrequency rf voltages occurring in vacuum by proper layout and shape of components, limit the component's surface/volumes where the rf voltage is high; (2) study the effects of magnetic insulation, as applied to the current design; (3) provide electrical characteristics of the antenna for the development and analysis of tuning, arc detection/suppression, and systems for discriminating between arcs and edge-localized modes (ELMs); (4) maintain close interface with mechanical design

[en] The coupling between the ion cyclotron (IC) antenna and the ITER plasma (as expressed by the load resistance the antenna sees) will experience relatively fast variations due to plasma edge profile modifications. If uncompensated, these will cause an increase in the amount of power reflected back to the transmitter and ultimately a decrease in the amount of radio frequency (rf) power to the plasma caused by protective suppression of the amount of rf power generated by the transmitter. The goals of this task were to study several alternate designs for a tuning and matching (T ampersand M) system and to recommend some research and development (R ampersand D) tasks that could be carried out to test some of the most promising concepts. Analyses of five different T ampersand M configurations are presented in this report. They each have different advantages and disadvantages, and the choice among them must be made depending on the requirements for the IC system. Several general conclusions emerge from our study: The use of a hybrid splitter as a passive reflected-power dump [''edge localized mode (ELM)-dump''] appears very promising; this configuration will protect the rf power sources from reflected power during changes in plasma loading due to plasma motion or profile changes (e.g., ELM- induced changes in the plasma scrape-off region) and requires no active control of the rf system. Trade-offs between simplicity of design and capability of the system must be made. Simple system designs with few components near the antenna either have high voltages over considerable distances of transmission lines, or they are not easily tuned to operate at different frequencies. Designs using frequency shifts and/or fast tuning elements can provide fast matching over a wide range of plasma loading; however, the designs studied here require components near the antenna, complicating assembly and maintenance. Capacitor-tuned resonant systems may offer a good compromise

[en] A theoretical treatment of heating of tokamak plasmas by relativistic electron beam (REB) injection is presented. Comparisons with prior work and considerations for both research and reactor sized systems are included. Guiding center orbits for beam electrons in a tokamak are obtained and requirements for significant beam penetration of the plasma are determined. Interaction mechanisms of the beam with the plasma are reviewed and ion heating and runaway problems are considered. Results indicate that, under a reasonable set of assumptions:(1) The REB can be injected to penetrate into the plasma volume and will be trapped in the plasma; (2) The beam should heat the plasma electrons due to beam-plasma instability or return current heating, and some direct ion heating may occur; (3) The classical rate of energy transfer from electrons to ions would be great enough in a system satisfying the Lawson condition to convert much of the REB energy to ion energy, in case direct ion heating did not occur. (U.S.)

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