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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

10.1002/ange.19600721118

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ISSN

1572-9591

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Calculation of Beam Extraction Pulse Duration for

Authors: Yongjian Xu Chundong Hu Yuanlai Xie Qiang Guo Ling Tao
Publish Date: 2010/04/14
Volume: 29, Issue: 4, Pages: 395-398
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Abstract

Distributed thermocouple measurement will be used on EAST neutral beam injection beam angular divergence measurement In order to determine the pulse duration of neutral beam extraction the plates of calorimeter are analyzed by using heat transfer science Mathematic derivations and the results are given according to the installation location of thermocouple in the plate Those results could point the way to beam angular divergence measurement of EAST neutral beam injection

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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. Determination of Average Ion Temperature of the TVD Tokamak by a Simple Charge Exchange Analyzer Detector
  16. Application of High Energy Protons in Inertial Confinement Fusion by Using the Fast Ignitor Concept for DT Fusion
  17. Numerical Evaluation on Heat Shock Resistance of Two ITER-Like First Wall Mockups
  18. The Plasma Liner Compression Experiment
  19. Spheromak Formation and Current Sustainment Using a Repetitively Pulsed Source
  20. Erratum to: Kilotesla Magnetic Assisted Fast Laser Ignited Boron-11 Hydrogen Fusion with Nonlinear Force Driven Ultrahigh Accelerated Plasma Blocks
  21. Plasma Magnetic Fluctuations Measurement on the Outer Surface of IR-T1 Tokamak
  22. Stability of Plasma Configurations During Compression
  23. Investigation on the Neutronic Performance of a Fusion Reactor Using Flibe with Heavy Metal Fluorides
  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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