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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/lsm.20269

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1572-9591

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Structure Analysis of High Current DC Disconnector

Authors: Zhiquan Song Yong Yang Chuan Li P Fu X Q Zhang Lin Dong Min Wang Tongzhen Fang
Publish Date: 2014/11/26
Volume: 34, Issue: 2, Pages: 398-404
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Abstract

This paper presents the structure analysis of the high current dc disconnector DCDS used in ITER poloidal field converter As the DCDS has to withstand 350 kA short current and meet high insulation level requirement the dynamic stability structure analysis and insulation structure analysis based on finite element method are given in details respectively And corresponding tests of the DCDS prototype are also done to verify the structure analysis results The analysis and test results indicate the DCDS prototype can fully satisfy the design requirements

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  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)
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  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
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