Localized direct electron heating by mode-converted ion cyclotron range of frequencies (ICRF) waves in D(H) tokamak plasmas has been clearly observed for the first time in Alcator C-Mod. Both on- and off-axis (high field side) mode conversion electron heating (MCEH) have been observed. The MCEH profile was obtained from a break in slope analysis of electron temperature signals in the presence of rf (radio frequency) shut-off. The temperature was measured by a 32-channel high spatial resolution (7 mm) 2nd harmonic heterodyne electron cyclotron emission (ECE) system. The experimental profiles were compared with the predictions from a toroidal full-wave ICRF code TORIC. Using the hydrogen concentration measured by a high-resolution optical spectrometer, TORIC predictions were shown qualitatively in agreement with the experimental results for both on- and off-axis MC cases. From the simulations, the electron heating from mode converted ion cyclotron wave (ICW) and ion Bernstein wave (IBW) is examined.

This book provides a comprehensive look at the state of the art of externally driven and self-generated rotation as well as momentum transport in tokamak plasmas. In addition to recent developments, the book includes a review of rotation measurement techniques, measurements of directly and indirectly driven rotation, momentum sinks, self-generated flow, and momentum transport. These results are presented alongside summaries of prevailing theory and are compared to predictions, bringing together both experimental and theoretical perspectives for a broad look at the field. Both researchers and graduate students in the field of plasma physics will find this book to be a useful reference. Although there is an emphasis on tokamaks, a number of the concepts are also relevant to other configurations.

The tokamak is the principal tool in controlled fusion research. This book acts as an introduction to the subject and a basic reference for theory, definitions, equations, and experimental results. The fourth edition has been completely revised, describing their development of tokamaks to the point of producing significant fusion power.

A population of suprathermal ions has been observed in the scrape-off layer during injection of power in the ion cyclotron frequency range on the Alcator C-Mod tokamak. These ions generated energetic neutrals measured with a charge-exchange neutral particle analyzer. In the hydrogen minority heating regime, fast particles were generated only when the injected power was above 500kW. Fast particles were observed at a low level of injected power when the frequency was a multiple of the ion cyclotron frequency in the scrape-off layer. The power deposited in the edge was always less than a few percent of the injected power and did not increase impurity levels. The theoretical threshold of parametric decay instabilities for decay of the pump wave in the antenna near field into an ion Bernstein wave and an ion cyclotron quasimode matches the observed threshold for fast ion production under a variety of conditions.

The complete ion cyclotron range of frequency (ICRF) heating system for the Tokamak Fusion Test Reactor (TFTR), consisting of four antennas and six generators designed to deliver 12.5 MW to the TFTR plasma, has now been installed. Recently a series of experiments has been conducted to explore the effect of ICRF heating on the performance of low recycling, Supershot plasmas in minority and non-resonant electron heating regimes. The addition of up to 7.4 MW of ICRF power to full size (R ∼ 2.6 m, a ∼ 0.95 m), helium-3 minority, deuterium Supershots heated with up to 30 MW of deuterium neutral beam injection has resulted in a significant increase in core electron temperature (?T{sub e}=3--4 key). Simulations of equivalent deuterium-tritium (D-T) Supershots predict that such ICRF heating should result in an increase in ?{sub alpha}(O) ∼ 30%. Direct electron heating has been observed and has been found to be in agreement with theory. ICRF heating has also been coupled to neutral beam heated plasmas fueled by frozen deuterium pellets. In addition ICRF heated energetic ion tails have been used to simulate fusion alpha particles in high recycling plasmas. Up to 11.4 MW of ICRF heating has been coupled into a hydrogen minority, high recycling helium plasma and the first observation of the toroidal Alfven eigenmode (TAE) instability driven by the energetic proton tail has been made in this regime.