Advertisement

Journal of Fusion Energy

, Volume 38, Issue 2, pp 236–243 | Cite as

Control and Protection Strategy Design of ITER Toroidal Field Coil Power Supply System

  • Renjing FanEmail author
  • Jun Tao
  • Inyoung Suh
  • Peng Fu
  • Ignacio Prieto
Original Research
  • 80 Downloads

Abstract

Eighteen Toroidal Field (TF) coils are operated on steady-state mode at highest current of 68 kA in comparison with the other pulse operation coils such as Poloidal Field and Central Solenoid coils in ITER superconductive magnet system, which are fed by Coil Power Supply Systema (CPSS). The reliability of TF circuit is significant to investment and nuclear safety of ITER machine. Hence, the comprehensive protection functions as Slow Discharge, Accelerated Discharge and Fast Discharge are required by ITER TF CPSS and the detailed realizations have been illustrated according to the different levels of faults to guarantee the safety of components including TF coils. In addition, the simulation model has been built by MATLAB/SIMULINK according to the real configuration of circuit and control system to verify the protection strategies and the satisfied simulation results have been obtained.

Keywords

ITER Toroidal field Coil power supply Protection strategy Safety 

Notes

Acknowledgements

The authors wish to thank the technical teams of the Korean and Russian Federation DAs that contributed to the Design of the ITER TF CPSS.

References

  1. 1.
    J. Tao et al., ITER coil power supply and distribution system, in Proceedings–Symposium Fusion Engineering, (IEEE, Chicago, 2011), pp. 1–8Google Scholar
  2. 2.
    S. Huang et al., Fabrication and quality assurance of ITER TF conductor in China. Fusion Eng. Des. 131, 33–40 (2018)CrossRefGoogle Scholar
  3. 3.
    J.S. Oh et al., Preliminary design of the ITER AC/DC converters supplied by the Korean domestic agency. Fusion Eng. Des. 88, 1555–1559 (2013)CrossRefGoogle Scholar
  4. 4.
    I. Song et al., Fault analysis of ITER coil power supply system, in Selected Topics in Power Systems and Remote Sensing (2010), pp. 153–158Google Scholar
  5. 5.
    V. Marchese et al., Circuit analysis and control of the power supply system for the testing of ITER TF model coil. Fusion Eng. Des. 58–59, 69–73 (2001)CrossRefGoogle Scholar
  6. 6.
    H. Yuan et al., Analysis of internal and external bypass circuit design for ITER poloidal field converter system. J. Fusion Energ. 33, 577–581 (2014)CrossRefGoogle Scholar
  7. 7.
    R. Zanino et al., Quench analysis of an ITER TF coil. Fusion Eng. Des. 85, 752–760 (2010)CrossRefGoogle Scholar
  8. 8.
    J. Goff et al., The ITER magnet power supplies and control system, in International conference on electrical machines and systems (IEEE, Incheon, 2010), pp. 346–351Google Scholar

Copyright information

© Springer Science+Business Media, LLC, part of Springer Nature 2019

Authors and Affiliations

  1. 1.Institute of Plasma Physics, Hefei Institutes of Physical ScienceChinese Academy of SciencesHefeiChina
  2. 2.University of Chinese Academy of SciencesBeijingChina
  3. 3.ITER OrganizationSt. Paul Lez Durance CEDEXFrance
  4. 4.Anhui UniversityHefeiChina

Personalised recommendations