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Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma

Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma PDF Author: Kin-lu Wong
Publisher:
ISBN:
Category : Deuterium
Languages : en
Pages : 146

Book Description


Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma

Fast Wave Propagation and Minority Ion Heating Current Drive in a Two-ion Species Tokamak Plasma PDF Author: Kin-lu Wong
Publisher:
ISBN:
Category : Deuterium
Languages : en
Pages : 146

Book Description


Wave Heating and Current Drive in Plasmas

Wave Heating and Current Drive in Plasmas PDF Author: Victor L. Granatstein
Publisher: CRC Press
ISBN: 9782881240577
Category : Science
Languages : en
Pages : 524

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 444

Book Description


Tokamaks

Tokamaks PDF Author: John Wesson
Publisher: Oxford University Press
ISBN: 0199592233
Category : Science
Languages : en
Pages : 828

Book Description
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.

Fast Wave Heating and Current Drive in Tokamak Plasmas with Negative Central Shear

Fast Wave Heating and Current Drive in Tokamak Plasmas with Negative Central Shear PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

Book Description
Fast waves provide an excellent tool for heating electrons and driving current in the central region of tokamak plasmas. In this paper, we report the use of centrally peaked electron heating and current drive to study transport in plasmas with negative central shear (NCS). Tokamak plasmas with NCS offer the potential of reduced energy transport and improved MHD stability properties, but will require non-inductive current drive to maintain the required current profiles. Fast waves, combined with neutral beam injection, provide the capability to change the central current density evolution and independently vary {ital T{sub e}}, and {ital T{sub i}} for transport studies in these plasmas. Electron heating also reduces the collisional heat exchange between electrons and ions and reduces the power deposition from neutral beams into electrons, thus improving the certainty in the estimate of the electron heating. The first part of this paper analyzes electron and ion heat transport in the L-mode phase of NCS plasmas as the current profile resistively evolves. The second part of the paper discusses the changes that occur in electron as well as ion energy transport in this phase of improved core confinement associated with NCS.

Fusion Energy Update

Fusion Energy Update PDF Author:
Publisher:
ISBN:
Category : Controlled fusion
Languages : en
Pages : 160

Book Description


The Journal of the Korean Physical Society

The Journal of the Korean Physical Society PDF Author:
Publisher:
ISBN:
Category : Physics
Languages : en
Pages : 942

Book Description


Predictions of Fast Wave Heating, Current Drive, and Current Drive Antenna Arrays for Advanced Tokamaks

Predictions of Fast Wave Heating, Current Drive, and Current Drive Antenna Arrays for Advanced Tokamaks PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 8

Book Description
The objective of the advanced tokamak program is to optimize plasma performance leading to a compact tokamak reactor through active, steady state control of the current profile using non-inductive current drive and profile control. To achieve these objectives requires compatibility and flexibility in the use of available heating and current drive systems--ion cyclotron radio frequency (ICRF), neutral beams, and lower hybrid. For any advanced tokamak, the following are important challenges to effective use of fast waves in various roles of direct electron heating, minority ion heating, and current drive: (1) to employ the heating and current drive systems to give self-consistent pressure and current profiles leading to the desired advanced tokamak operating modes; (2) to minimize absorption of the fast waves by parasitic resonances, which limit current drive; (3) to optimize and control the spectrum of fast waves launched by the antenna array for the required mix of simultaneous heating and current drive. The authors have addressed these issues using theoretical and computational tools developed at a number of institutions by benchmarking the computations against available experimental data and applying them to the specific case of TPX.

Dissertation Abstracts International

Dissertation Abstracts International PDF Author:
Publisher:
ISBN:
Category : Dissertations, Academic
Languages : en
Pages : 700

Book Description


Fast Wave Current Drive Experiment on the DIII-D Tokamak

Fast Wave Current Drive Experiment on the DIII-D Tokamak PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 4

Book Description
One method of radio-frequency heating which shows theoretical promise for both heating and current drive in tokamak plasmas is the direct absorption by electrons of the fast Alfven wave (FW). Electrons can directly absorb fast waves via electron Landau damping and transit-time magnetic pumping when the resonance condition [omega] - [kappa]{sub {parallel}e}[upsilon]{sup {parallel}e} = O is satisfied. Since the FW accelerates electrons traveling the same toroidal direction as the wave, plasma current can be generated non-inductively by launching FW which propagate in one toroidal direction. Fast wave current drive (FWCD) is considered an attractive means of sustaining the plasma current in reactor-grade tokamaks due to teh potentially high current drive efficiency achievable and excellent penetration of the wave power to the high temperature plasma core. Ongoing experiments on the DIII-D tokamak are aimed at a demonstration of FWCD in the ion cyclotron range of frequencies (ICRF). Using frequencies in the ICRF avoids the possibility of mode conversion between the fast and slow wave branches which characterized early tokamak FWCD experiments in the lower hybrid range of frequencies. Previously on DIII-D, efficient direct electron heating by FW was found using symmetric (non-current drive) antenna phasing. However, high FWCD efficiencies are not expected due to the relatively low electron temperatures (compared to a reactor) in DIII-D.