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Journal of Fusion Energy

, Volume 36, Issue 1, pp 15–20 | Cite as

Calculation of the Heat Flux on the First Wall During Disruption on Tokamak

  • Zhendong Yang
  • Shuangbao Shu
  • Kaifu Gan
  • Jianan Fang
  • Bin Zhang
Original Research
  • 202 Downloads

Abstract

Disruptions are the most dangerous instabilities in tokamak plasma. During plasma disruption, the large amounts of energy will be deposited on Plasma Facing Components (PFCs) which is a damaging threat for the divertor target and the first wall materials. Therefore, studying the characteristic of heat deposition on the first wall is very significant. The Infrared (IR) camera is an effective tool to measure the surface temperature profile on the first wall on the Experimental Advanced Superconducting Tokamak (EAST). With a finite difference method, the heat flux arrived to the divertor can be calculated from the surface temperature. However, the surface layer on the divertor has a great influence on the calculation of the heat flux on the divertor. The numerical method for solving heat conduction for semi-infinite model is given in this paper. And the thermal resistance of surface layers is considered in this numerical method. In addition, the distribution of heat flux on the divertor during disruption is also shown.

Keywords

Infrared camera Tokamak Plasma disruption Heat flux 

Notes

Acknowledgements

The authors are grateful to all members of the EAST team for their contribution to the experiments. This work is supported by the National Natural Science Foundation of China (Grant No. 11105028), and the National Magnetic Confinement Fusion Science Program of China (No. 2013GB102001, No. 2015GB102004).

References

  1. 1.
    G. Arnoux, A. Loarte, V. Riccardo et al., Nucl. Fusion 49, 085038 (2009)ADSCrossRefGoogle Scholar
  2. 2.
    T.C. Hender, J.C. Wesley, J. Bialek et al., Nucl. Fusion 47, S128–S202 (2007)ADSCrossRefGoogle Scholar
  3. 3.
    E. Delchambre, G. Counsell, A. Kirk et al., J. Nucl. Mater. 363, 1409 (2007)ADSCrossRefGoogle Scholar
  4. 4.
    P. Andrew, A. Alonzo, G. Arnoux et al., J. Nucl. Mater. 363, 1026 (2007)ADSGoogle Scholar
  5. 5.
    V. Riccardo, A. Loarte et al., Nucl. Fusion 45, 1427 (2005)ADSCrossRefGoogle Scholar
  6. 6.
    B. Wan, J. Li, H. Guo et al., Nucl. Fusion 55, 104015 (2015)ADSCrossRefGoogle Scholar
  7. 7.
    Y.X. Wan, 2006 Overview progress and future plan of EAST Project. in Proc. 21st IAEA FEC 2006 (Chengdu, People’s Republic of China, 2006) (Vienna: IAEA) OV/1-1Google Scholar
  8. 8.
    D.R. Pitts, L.E. Sissom, Schaum’s Outline of Theory and Problems of Heat Transfer, 2nd edn. (the McGraw-Hill companies, 1998)Google Scholar
  9. 9.
    T. Eich, P. Andrew, A. Herrmann, W. Fundamenski, A. Loarte, R.A. Pitts, JET-EFDA contributors, Plasma Phys. Control Fusion 49, 573–604 (2007)ADSCrossRefGoogle Scholar
  10. 10.
    P.C. de Vries, G. Aronoux, A. Huber et al., Plasma Phys. Control Fusion 12, 54 (2012)Google Scholar

Copyright information

© Springer Science+Business Media New York 2016

Authors and Affiliations

  1. 1.Tongling UniversityTonglingChina
  2. 2.Institute of Plasma PhysicsChinese Academy of SciencesHefeiChina
  3. 3.School of Instrument Science and Opto-electronics EngineeringHefei University of TechnologyHefeiChina
  4. 4.College of ScienceDonghua UniversityShanghaiChina

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