Concept Design of CFETR Tokamak Machine

@article{Song2014ConceptDO,
  title={Concept Design of CFETR Tokamak Machine},
  author={Y. Song and S. Wu and J. Li and B. Wan and Y. X. Wan and P. Fu and M. Y. Ye and J. X. Zheng and K. Lu and X. Gao and Su Mei Liu and X. F. Liu and M. Z. Lei and X. B. Peng and Y. Chen},
  journal={IEEE Transactions on Plasma Science},
  year={2014},
  volume={42},
  pages={503-509}
}
  • Y. Song, S. Wu, +12 authors Y. Chen
  • Published 2014
  • Computer Science
  • IEEE Transactions on Plasma Science
  • China Fusion Engineering Test Reactor (CFETR) is a tokamak reactor; one design option under the consideration of the China National Integration Design Group employs superconducting magnets. The fusion power is at the range of 50-200 MW and the duty cycle (or burning time) was envisioned as 30%-50%. The plasma current will be 10 MA and the major and minor radii are 5.7 and 1.6 m, respectively. The concept engineering design including the magnet system, vacuum vessel (VV) system, and maintenance… CONTINUE READING
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    References

    SHOWING 1-10 OF 16 REFERENCES
    Concept design of CFETR Tokamak machine
    • 16
    Concept design of CFETR superconducting magnet system based on different maintenance ports
    • 54
    Design of the HT-7U tokamak device
    • S. T. Wu, W. Wu, +15 authors Y. Chao
    • Physics
    • 18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050)
    • 1999
    • 12
    Overview of steady state operation of HT-7 and present status of the HT-7U project
    • 173
    Plasma facing components of EAST
    • 27
    The European contribution to the procurement of the ITER Remote Handling systems
    • 8
    Principal Physics Developments Evaluated in the ITER Design Review
    • 179
    • PDF