Skip to main content
SpringerLink
Log in

EAST Full Tungsten Divertor Design

  • Original Research
  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

One of the most important research goals of EAST concerns long steady-state high-performance plasma pulse. It is a fusion engineering challenge for divertor to handle steady-state high heat flux form plasma. To accomplish this aim, full tungsten divertor has been designed for EAST to withstand high heat flux which is increasing rapidly. Full tungsten divertor is an ITER-like design which consists of monoblock units, end boxes and cassette body. The newest divertor of EAST will withstand more than 10 MW/m2 heat flux in target zone. The full tungsten divertor should be reliable during plasma discharge campaign to reduce the failure risk of plasma components under critical thermal power from plasma. Analysis and experiment results proved full tungsten divertor of EAST will be very reliable for future long steady-state high-performance plasma pulse. The design and application of full tungsten divertor of EAST can also bring experiences and answers for ITER or any next divertor fusion device on nuclear phase.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6

Similar content being viewed by others

References

  1. Y.X. Wan, P.D. Weng, J.G. Li et al. Progress of EAST project in China, FT/3-3 (2005)

  2. B.J. Xiao, J.Li, J.R. Luo, et al. The first diverted plasma on EAST Tokamak, 34th EPS conference on plasma phys. ECA Vol.31F, P-4.014 Warsaw, 2–6 July 2007 (2007)

  3. Q. Jinping, G. Xianzu, L. Jiangang et al., Operation with 1 MA plasma current in EAST. Plasma Sci. Technol. 13(1), 1–2 (2011)

    Article  Google Scholar 

  4. L. Cao, Y.T. Song, The loosing mechanism of screw bolts on the first graphite tiles in EAST. Fusion Eng. Des. 86, 1710–1713 (2011)

    Article  Google Scholar 

  5. C. Lei, S. Yuntao, Preload analysis of screw bolt joints on the first wall graphite tiles in east. Plasma Sci. Technol. 14(9), 850–854 (2012)

    Article  Google Scholar 

  6. C. Liang, M. Ye, D. Yao et al., The structure analysis of the EAST updated divertor. J. Fusion Energ. 33(5), 471–475 (2014)

    Article  Google Scholar 

  7. L.I. Lei, Y. Damao, L. Changle et al., Optimization of the water-cooled Structure for the divertor plates in EAST based on an orthogonal theory. Plasma Sci. Technol. 17(5), 435–440 (2015)

    Article  ADS  Google Scholar 

  8. Q. Li, S. Qin, W. Wang et al., Manufacturing and testing of W/Cu mono-block small scale mock-up for EAST by HIP and HRP technologies. Fusion Eng. Des. 88(9–10), 1808–1812 (2013)

    Article  Google Scholar 

  9. Q. Li, P. Qi, H.S. Zhou et al., R&D issues of W/Cu divertor for EAST. Fusion Eng. Des. 85(7–9), 1106–1112 (2010)

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

  1. Institute of Plasma Physics, CAS, Hefei, China

    Lei Cao, Zibo Zhou & Damao Yao

Authors
  1. Lei Cao
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Zibo Zhou
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Damao Yao
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Lei Cao.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Cao, L., Zhou, Z. & Yao, D. EAST Full Tungsten Divertor Design. J Fusion Energ 34, 1451–1456 (2015). https://doi.org/10.1007/s10894-015-9951-2

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-015-9951-2

Keywords

Search

Navigation