Shijun Du

ORCID: 0009-0007-2049-0069
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About
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Research Areas
  • Superconducting Materials and Applications
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Particle accelerators and beam dynamics
  • Spacecraft and Cryogenic Technologies
  • Microstructure and Mechanical Properties of Steels
  • Geotechnical and Geomechanical Engineering
  • Plasma Diagnostics and Applications
  • Magnetic Properties and Applications
  • Thermal Analysis in Power Transmission
  • High-Velocity Impact and Material Behavior
  • Metal Forming Simulation Techniques
  • Metallurgy and Material Forming
  • Electromagnetic Launch and Propulsion Technology
  • Electromagnetic Simulation and Numerical Methods
  • Metal and Thin Film Mechanics
  • Mechanical Engineering and Vibrations Research

Institute of Plasma Physics
1995-2024

Chinese Academy of Sciences
2008-2024

Hefei Institutes of Physical Science
2016

Centre of Plasma Physics - Institute for Plasma Research
2013

Czech Academy of Sciences, Institute of Plasma Physics
2013

Hefei University of Technology
2006

Abstract Since the last IAEA-FEC in 2021, significant progress on development of long pulse steady state scenario and its related key physics technologies have been achieved, including reproducible 403 s long-pulse steady-state H-mode plasma with pure radio frequency (RF) power heating. A thousand-second time scale (∼1056 s) fully non-inductive high injected energy up to 1.73 GJ has also achieved. The EAST operational regime β P significantly extended ( H 98y2 > 1.3, ∼ 4.0, N 2.4 n e / GW...

10.1088/1741-4326/ad4270 article EN cc-by Nuclear Fusion 2024-04-24

10.1016/j.fusengdes.2008.11.011 article EN Fusion Engineering and Design 2008-12-21

10.1016/j.fusengdes.2006.03.003 article EN Fusion Engineering and Design 2006-05-05

10.1016/j.fusengdes.2008.07.022 article EN Fusion Engineering and Design 2008-09-03

The Comprehensive Research Facility for Fusion Technology (CRAFT) is a prominent national science facility in China, and the toroidal field (TF) coil major constituent of China Engineering Test Reactor (CFETR). In order to master core technology manufacturing process large magnets, cable-in-conduit conductor (CICC) used design TF structure an important component CRAFT system, which facilitates manufacture prototype coils CFETR. Design lifting solutions crucial oversized overweight coils, as...

10.1109/tasc.2024.3377697 article EN IEEE Transactions on Applied Superconductivity 2024-03-18

Thermal analysis of the equatorial thermal shield for ITER is conducted in order to confirm that cooling tube design was reasonable under both plasma operational and baking conditions. The structural performance analyzed by means finite element software ANSYS. A comparison results with requirements shows simulation are within allowable requirements, which indicates feasibility reliability structure.

10.1088/1009-0630/14/10/14 article EN Plasma Science and Technology 2012-10-01

A numerical method for calculating plasma equilibrium in a tokamak with an iron core transformer is presented. The influence of the on considered as action currents imaginary external poloidal coils. Coupling coefficients allow precomputation effects equilibrium. problem then converted into solving MHD equation air tokamak. calculation region reduced to minimum

10.1088/0029-5515/35/3/i09 article EN other-oa Nuclear Fusion 1995-03-01

Performance test of the China Fusion Engineering Test Reactor (CFETR) central solenoid (CS) and toroidal field (TF) insert coils is great importance to evaluate CFETR magnet performance in relevant operation conditions. The superconducting coil facility for being designed with aim providing a background magnetic CS TF coils. consists inner module Nb3Sn outer NbTi coil. have maximum 12.59 T stored energy 436.6 MJ. An active quench protection circuit positive temperature coefficient dump...

10.1186/s40064-016-3706-z article EN SpringerPlus 2016-12-01

The Comprehensive Research Facility for Fusion Technology (CRAFT) is a prominent national science facility in China, and the toroidal field (TF) coil testing model built at CRAFT major constituent of China Engineering Test Reactor (CFETR). cable-in-conduit conductor (CICC) used to design TF structure an important component system, which facilitates manufacture prototype coils CFETR. This study mainly elucidates impact that structural lifting adapters has on assembly embedding via sub winding...

10.2139/ssrn.4597483 preprint EN 2023-01-01
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