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Full Time Discharge Simulation and Plasma Profile Control for CFETR

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Abstract

Tokamak Simulation Code (TSC) is a numerical model of an axisymmetric free boundary tokamak plasma and the associated control systems. The time dependence of ohmic discharges of China Fusion Engineering Test Reactor (CFETR) has been simulated using TSC in this work. According to the CFETR design requirements, the poloidal field coils current waveforms are designed. The ramp up, flat top in single-null configuration ohmic discharge plasma current are simulated by the CS and PF coils current waveforms. Displacement feedback system and current feedback system are used to control the plasma from the limiter shape to the divertor shape. Major radius, minor radius, triangle deformation, elongation, plasma configuration and volt-second consumption are obtained. The calculation results can be beneficial to provide the references for CFETR physics design and components design.

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References

  1. J. Zheng, X. Liu, Y. Song et al., Concept design of CFETR superconducting magnet system based on different maintenance ports. Fusion Eng. Des. 88, 2960–2966 (2013)

    Article  Google Scholar 

  2. S.C. Jardin, N. Pomphrey, F. Hoffmann, Dynamic modeling of transport and positional control of tokamaks. J. Comput. Phys. 66, 481 (1986)

    Article  ADS  MATH  Google Scholar 

  3. F. Hoffman, S.C. Jardin et al., Application of a new algorithm to plasma shape cotrol in BPX. Nucl. Fusion 32, 897 (1992)

    Article  ADS  Google Scholar 

  4. R.J. Hawryluk, D.J. Campbell, G. Janeschitz, P.R. Thomas, R. Albanese, R. Ambrosino et al., Principal physics developments evaluated in the ITER design review. Nucl. Fusion 49, 065012 (2009)

    Article  ADS  Google Scholar 

  5. K. Tomabechi, J.R. Gilleland, YuA Sokolov, ITER conceptual design. Nucl. Fusion 31, 1135 (1991)

    Article  Google Scholar 

  6. Y.X. Wan, Overview of steady state operation of HT-7 and present status of the HT-7U project. Nucl. Fusion 40, 1050 (2000)

    Article  ADS  Google Scholar 

  7. F. Najmabadi, the ARIES Team, Overview of ARIES-RS Tokamak fusion power plant. Fusion Eng. Des. 41, 365–370 (1998)

    Article  Google Scholar 

  8. CFETR Design Group, Report on conceptual design of CFETR Tokamak Machine v1.1, in Proceedings of 2nd Workshops MFE Develop. Strategy, Hefei, China, 2012, pp. 20–25

  9. B. Wu, Discharge simulation of HT-7U Tokamak, [Ph. D], Hefei, Institute of Plasma Physics, Chinese Academy of Sciences, 2002 (in Chinese)

  10. S.C. Jardin, M.G. Bell, N. Pomphrey, Nucl. Fusion 33, 371 (1993)

    Article  ADS  Google Scholar 

  11. S.C. Jardin, J. Menard, C. Kessel, S. Kaye, A.H. Glasser, Modelling of NSTX plasma with the Tokamak Simulation Code (TSC), in Innovative Confinement Concepts Meeting LBL, 22–24 Feb 2000

  12. N. Xingping, Simulation of the deformationand evolution of the plasma configuration for EAST. [Master Thesis]. Hefei: ASIPP2006 (in Chinese)

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Acknowledgments

This work is supported by the National Magnetic Confinement Fusion Science Program of China under Grant Nos. 2013GB113004 and 2015GB121007 and also by the National Natural Science Foundation of China with Grant Nos. 51576208 and 11505290.

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Authors and Affiliations

  1. New Star Institute of Applied Technology, Hefei, 230031, Anhui, People’s Republic of China

    Rongfei Wang, Jinhong Yang, Weihua Wang, Bo Shi & Jiajia Han

  2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, 230031, Anhui, People’s Republic of China

    Weihua Wang, Bo Shi & Jiajia Han

Authors
  1. Rongfei Wang
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  2. Jinhong Yang
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  3. Weihua Wang
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  4. Bo Shi
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  5. Jiajia Han
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Correspondence to Rongfei Wang.

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Wang, R., Yang, J., Wang, W. et al. Full Time Discharge Simulation and Plasma Profile Control for CFETR. J Fusion Energ 35, 440–445 (2016). https://doi.org/10.1007/s10894-016-0058-1

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  • DOI: https://doi.org/10.1007/s10894-016-0058-1

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