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Title of Journal: J Fusion Energ

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Abbravation: Journal of Fusion Energy

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Springer US

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DOI

10.1007/s10894-016-0102-1

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1572-9591

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Determination of Average Ion Temperature of the TV

Authors: M Kazemi M Habibi R Amrollahi
Publish Date: 2016/06/16
Volume: 35, Issue: 5, Pages: 743-747
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Abstract

In this paper the average ion temperature of the TVD tokamak plasma is determined by a low cost charge exchange analyzer When the neutral beam energy was equal to 3 keV the stripping efficiency was 0065 Estimated average ion temperatures for cold and hot regions of the plasma were 100 and 650 eV respectively Unlike the cold region of the plasma in which ion temperature was not related to the time ion temperature in the hot region was maximum when the plasma current reached its maximum value

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Other Papers In This Journal:
  1. Erratum to: The Study of the Dynamics of Z Pinch Plasma Using Electromagnetic, Thermal and Circuital Coupling
  2. Design and Fabrication of a Data Acquisition System for Pulsed Neutron Flux Measurement of Plasma Focus Devices
  3. Investigation of Arc Regulation of Hot Cathode Ion Source with Langmuir Probe
  4. Comments to the Article “The Behavior of Radial Electric Field and Toroidal Rotation in the Edge Plasma of Divertor Tokamak” by A. H. Bekheit Published in J. Fusion Energy (2010) 29, p. 443–446
  5. Evaluation of Heat Transfer Augmentation in a Nanofluid-Cooled Microchannel Heat Sink
  6. Measurement of Plasma Energy Confinement Time in Presence of Resonant Helical Field in IR-T1 Tokamak
  7. On the Current Sharing Control of ITER Poloidal Field Converter
  8. Thermalization of Langmuir Wave Energy via the Stochastic Plasma Electron Acceleration
  9. Combined Effect of Ion Temperature and Magnetic Field on Collisionless Sheath Structure
  10. The Use of Plasma Actuators in Narrowband Active Noise Control
  11. Effect of Internal Breeding of Tritium and Helium-3 on the Ignition of an ICF Fuel Pellet
  12. Reaction Kinetics for the Synthesis of Li 4 SiO 4 by Solid State Reaction from Li 2 SiO 3 and Li 2 CO 3 for Tritium Breeder
  13. Condensed Atomic Hydrogen as a Possible Target in Inertial Confinement Fusion (ICF)
  14. Structure Analysis of High Current DC Disconnector Used in ITER Poloidal Field Converter
  15. Application of High Energy Protons in Inertial Confinement Fusion by Using the Fast Ignitor Concept for DT Fusion
  16. Numerical Evaluation on Heat Shock Resistance of Two ITER-Like First Wall Mockups
  17. The Plasma Liner Compression Experiment
  18. Spheromak Formation and Current Sustainment Using a Repetitively Pulsed Source
  19. Erratum to: Kilotesla Magnetic Assisted Fast Laser Ignited Boron-11 Hydrogen Fusion with Nonlinear Force Driven Ultrahigh Accelerated Plasma Blocks
  20. Plasma Magnetic Fluctuations Measurement on the Outer Surface of IR-T1 Tokamak
  21. Stability of Plasma Configurations During Compression
  22. Investigation on the Neutronic Performance of a Fusion Reactor Using Flibe with Heavy Metal Fluorides
  23. Calculation of Beam Extraction Pulse Duration for Beam Angular Divergence Measurement of EAST Neutral Beam Injection
  24. Electrical Parameter Measurement System of the Ion Source for EAST Neutral Beam Injector
  25. Magnetohydrodynamic Free Convective Flow Past an Infinite Vertical Porous Plate with Magnetic Induction
  26. Activation Analysis and Comparison of Bio-shield Under ITER and ASP Neutron Irradiation
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