Search Results - "Yao, D.M."

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  1. 1

    The first in-vessel cryopump for EAST divertor experiment by Hu, Q.S., Yao, D.M., Luo, G.N., Xie, H., Xu, C.S., Li, J.G., Wang, X.M.

    Published in Fusion engineering and design (01-12-2010)
    “…To operate divertor experiment, an in-vessel cryopump was installed on the EAST tokamak in 2008. It can limit gas impurity recycling from divertor region into…”
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    Journal Article Conference Proceeding
  2. 2

    Development and application of limiter Langmuir probe array in EAST by Liu, S.C., Liao, L., Wei, W.Y., Liang, Y., Xu, J.C., Cao, L., Li, S., Li, L., Meng, L.Y., Qian, J.P., Zang, Q., Wang, L., Xu, S., Cai, J., Yan, N., Ma, Q., Zhao, N., Chen, R., Hu, G.H., Liu, J.B., Liu, X.J., Ming, T.F., Li, L.T., Sun, Y., Zeng, L., Li, G.Q., Yao, D.M., Xu, G.S., Gong, X.Z., Gao, X.

    Published in Fusion engineering and design (01-07-2022)
    “…•A newly limiter langmuir probe (LLP) array has been developed in EAST.•The LLP array has been operated in EAST since 2021.•The commissioning of EAST LLP was…”
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    Journal Article
  3. 3

    Formation of snowflake diverted equilibria of CFETR by Li, H., Li, G.Q., Luo, Z.P., Yao, D.M., Guo, Y., Gao, X.

    Published in Fusion engineering and design (01-10-2017)
    “…The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present…”
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    Journal Article
  4. 4

    Evaluation of target-plate heat flux for a possible snowflake divertor in CFETR using SOLPS by Mao, S.F., Guo, Y., Peng, X.B., Luo, Z.P., Xiao, B.J., Song, Y.T., Yao, D.M., Zhu, S.Z., Ye, M.Y.

    Published in Journal of nuclear materials (01-08-2015)
    “…China Fusion Engineering Test Reactor (CFETR) is proposed as a good complement to ITER for demonstration of fusion energy. CFETR is based on both physics and…”
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    Journal Article
  5. 5

    Progress on in-vessel poloidal field coils optimization design for alternative divertor configuration studies on the EAST tokamak by Xiao, B.J., Luo, Z.P., Li, H., Li, G.Q., Wang, L., Wang, Z.L., Xu, G.S., Yao, D.M., Zhou, Z.B., Calabrò, G., Crisanti, F., Castaldo, A., Lombroni, R., Minucci, S., Ramogida, G.

    Published in Fusion engineering and design (01-09-2019)
    “…An upgrade to the lower divertor is currently being planned for EAST superconducting tokamak, aiming at reaching over 400 s long-pulse H-mode operations with a…”
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    Journal Article
  6. 6

    High creep resistance behavior of the cast Al–Cu alloy modified by nano-scale Pr x O y by Zhao, W.G., Wang, J.G., Zhao, H.L., Yao, D.M., Jiang, Q.C.

    “…Creep behavior of the unmodified and modified cast Al–Cu alloys was investigated at temperatures from 393 to 483 K in the tension test. The creep resistance…”
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    Journal Article
  7. 7
  8. 8

    The structure analysis of ITER cryostat based on the finite element method by Liang, Chao, Ye, M.Y., Yao, D.M., Cao, Lei, Zhou, Z.B., Xu, Teijun, Wang, Jian

    Published in Fusion engineering and design (01-01-2013)
    “…In the ITER project the cryostat is one of the most important components. Cryostat shall transfer all the loads that derive from the TOKAMAK inner basic…”
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    Journal Article
  9. 9

    Plasma facing components of EAST by Song, Y.T., Peng, X.B., Xie, H., Liu, X.F., Bao, L.M., Zhou, Z.B., Cao, L., Xu, T.J., Ji, X., Peng, Y.H., Zhu, N., Zhang, P., Wu, J.F., Wang, S.M., Wang, X.M., Hu, J.S., Xie, C.Y., Chen, J.L., Luo, G.N., Yao, D.M., Gao, D.M., Gong, X.Z., Fu, P., Li, J.G.

    Published in Fusion engineering and design (01-12-2010)
    “…EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and…”
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    Journal Article Conference Proceeding
  10. 10

    EAST in-vessel components design by Yao, D.M., Li, J.G., Song, Y.T., Du, S.J., Chen, J.L., Weng, P.D.

    Published in Fusion engineering and design (01-11-2005)
    “…Divertor and other in-vessel components are very important parts of EAST superconducting Tokamak. The primary purpose of these components is to protect the…”
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    Journal Article Conference Proceeding
  11. 11

    Thermal and mechanical analysis of the EAST plasma facing components by Song, Y.T., Yao, D.M., Wu, S.T., Weng, P.D.

    Published in Fusion engineering and design (01-11-2005)
    “…The Experimental Advanced Superconducting Tokamak (EAST) is an advanced steady-state plasma physics experimental device, which has a long pulse (60–1000 s)…”
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    Journal Article Conference Proceeding
  12. 12

    HT-7U vacuum vessel by Yao, D.M., Song, Y.T., Wu, S.T., Weng, P.D.

    Published in Fusion engineering and design (01-09-2003)
    “…The HT-7U superconducting tokamak is under construction. It is expected to complete the fabrication and installation in the next 2–3 years. Overall…”
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    Journal Article Conference Proceeding
  13. 13

    Test results and analyses of conductor short samples for HT-7U by Weng, P.D., Bruzzone, P., Chen, Z.M., Stepanov, B., Chen, J.L., Wang, F.T., Fang, J., Yao, D.M., Xiao, B.J., Bi, Y.F., Li, B.Z.

    Published in Cryogenics (Guildford) (01-03-2003)
    “…The experiments of Cable-in conduit conductor (CICC) short samples with high proportion of segregated copper strands have been carried out in SULTAN facility…”
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    Journal Article Conference Proceeding
  14. 14

    Design and structure analysis of the HT-7U vacuum vessel by Yao, D.M., Song, Y.T., Wu, S.T., He, Y.X., Wu, W.Y., Du, S.J.

    Published in Fusion engineering and design (01-11-2001)
    “…The vacuum vessel of the HT-7U superconducting tokamak has a full welded structure with double wall which will be filled with borated water is used for neutron…”
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    Journal Article Conference Proceeding
  15. 15

    The R&D progress of the EAST (HT-7U) superconducting tokamak by Wu, S.T., Wu, W.Y., Pan, Y.N., Yao, D.M., Liao, Z.Y., Yu, J., Li, B.Z., Chen, Z.M., Pan, W.J., Song, Y.T., Chen, W.G., Wei, J., Weng, P.O., Gao, D.M., Wan, Y.X., Li, J.G.

    “…The superconducting tokamak project HT-7U, aiming at steady-state advanced operation mode, will make a contribution to future steady-state tokamak reactors…”
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    Conference Proceeding
  16. 16

    Design of the HT-7U tokamak device by Wu, S.T., Wu, W.Y., Yao, D.M., Chen, Z.M., Bi, Y.F., Pan, Y.N., Li, B.Z., Liao, Z.Y., Yu, J., He, Y.X., Song, Y.T., Chen, W.G., Wu, X.B., Gao, D.J., Ji, A.H., Pan, W.J., Wu, D., Chao, Y.L.

    “…The HT-7U superconducting tokamak is an advanced steady-state plasma physics experimental device to be built at the Institute of Plasma Physics, the Chinese…”
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    Conference Proceeding