ABSTRACT. Energy confinement is studied in lower hybrid current driven (LHCD) plasmas in Alcator C in the density range ii = (1-8) x 1013 cm- 3. In LHCD plasmas, the stored energy in the electron tail Wail can be a significant fraction of the total stored energy W"*, especially at lower densities. At sufficiently low densities, the energy confinement time of the high energy electrons is expected to become shorter than their colli-sional energy slowing down time, and direct energy losses from the electron tail can become important in the overall power balance. The global energy confinement time, defined as rE* * = W**t/Ptot, is found to be compara-ble to or exceed that in ohmically heated (OH) plasmas at low densities n, < 3 x 1013 ...
First principle modeling of the lower hybrid (LH) current drive in tokamak plasmas is a longstanding...
Abstract. Energy confinement comparable to tokamak quality is achieved in the MST reversed field pin...
The important goal of adding to the bootstrap a fraction of non-inductive plasma current, which woul...
This is the final report for contract DE-FG03-99ER54528, ''Computational Support for Alternative Con...
A study on energy confinement times in currentless helical plasmas has indicated a preferable densit...
Progress in understanding lower hybrid current drive (LHCD) at high density has been made through ex...
Neoclassical ion heat conduction is the major energy loss mechanism in the center of an ohmically he...
The main research on the energy from thermonuclear fusion uses deuterium plasmas magnetically trappe...
Over the past several years, tokamak neutral beam injection experiments have evolved from the brute ...
The work of this thesis concerns a technological aspect of a tokamak fusion power reactor. A toroida...
The important goal of adding to the bootstrap current a more flexible tool, capable of producing and...
Recent stationary improved confinement experiments with current density profile modifications in non...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Recent two major topics of Large Helical Device (LHD) towards fusion relevant conditions, high-densi...
First principle modeling of the lower hybrid (LH) current drive in tokamak plasmas is a longstanding...
Abstract. Energy confinement comparable to tokamak quality is achieved in the MST reversed field pin...
The important goal of adding to the bootstrap a fraction of non-inductive plasma current, which woul...
This is the final report for contract DE-FG03-99ER54528, ''Computational Support for Alternative Con...
A study on energy confinement times in currentless helical plasmas has indicated a preferable densit...
Progress in understanding lower hybrid current drive (LHCD) at high density has been made through ex...
Neoclassical ion heat conduction is the major energy loss mechanism in the center of an ohmically he...
The main research on the energy from thermonuclear fusion uses deuterium plasmas magnetically trappe...
Over the past several years, tokamak neutral beam injection experiments have evolved from the brute ...
The work of this thesis concerns a technological aspect of a tokamak fusion power reactor. A toroida...
The important goal of adding to the bootstrap current a more flexible tool, capable of producing and...
Recent stationary improved confinement experiments with current density profile modifications in non...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Recent two major topics of Large Helical Device (LHD) towards fusion relevant conditions, high-densi...
First principle modeling of the lower hybrid (LH) current drive in tokamak plasmas is a longstanding...
Abstract. Energy confinement comparable to tokamak quality is achieved in the MST reversed field pin...
The important goal of adding to the bootstrap a fraction of non-inductive plasma current, which woul...