Search Results - "Weng, P.D."

The modifications of conductor design for HT-7U TF magnets by Weng, P.D., Chen, Z.M., Bi, Y.F., Li, B.Z., Wu, S.T., Wu, W.Y.

“…The Tokamak HT-7U project has been funded as a Chinese national project since 1998. The machine is designed by the Institute of Plasma Physics, Chinese Academy…”
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Preliminary engineering design of toroidal field magnet system for superconducting tokamak HT-7U by Pan, Y.N., Weng, P.D., Chen, Z.M., Li, B.Z., Wu, S.T., Wu, W.Y., Gao, B.J., Yu, J., Wu, D., Wu, X.B., Chen, Q., Chen, W.G.

“…HT-7U is a large fusion experimental device. It will be built at the Institute of Plasma Physics of Chinese Academy of Sciences. The mission of HT-7U is to…”
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Operational experience with forced cooled superconducting magnets by Ivanov, D.P., Kolbasov, B.N., Anashkin, I.O., Khvostenko, P.P., Pan, W.J., Pradhan, S., Sharma, A.N., Song, Y.T., Weng, P.D.

“…► Seventeen breakdowns happened in the fusion facilities with forced cooled superconducting magnets (FCSMs). ► The breakdowns always began on the electric,…”
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Technical diagnosis system for EAST tokamak by Qian, Jing, Weng, P.D., Luo, J.R., Chen, Z.M., Wu, Y.

“…Technical diagnosis system (TDS) is one of the important subsystems of EAST (experimental advanced superconducting tokamak) device, main function of which is…”
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Strain influence on J c behavior of Nb 3Sn multifilamentary strands fabricated by internal tin process for ITER by Zhang, P.X., Liang, M., Tang, X.D., Li, C.G., Xiao, C.J., Zhang, K., Zhou, L., Wu, Y., Weng, P.D., Lu, Y.F.

“…Superconducting properties of Nb 3Sn strands are much affected by the strain state of strands. More attention is concentrated on the influence of axial strain…”
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Strain influence on Jc behavior of Nb3sn multifilamentary strands fabricated by internal tin process for ITER by ZHANG, P. X, LIANG, M, TANG, X. D, LI, C. G, XIAO, C. J, ZHANG, K, ZHOU, L, WU, Y, WENG, P. D, LU, Y. F

“…Superconducting properties of Nb3Sn strands are much affected by the strain state of strands. More attention is concentrated on the influence of axial strain…”
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The engineering design of the HT-7U tokamak by Weng, P.D.

“…The HT-7U tokamak is a Chinese National Meg-science Engineering Project designed to develop scientific and technological basis for the tokamak fusion reactor…”
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Quench current measurement and performance evaluation of the EAST toroidal field coils by Weng, P.D., Chen, Z.M., Wu, Y., Tan, Y.F.

“…The EAST device (original name is HT-7U) is a superconducting tokamak being constructed at the Institute of Plasma Physics, Chinese Academy of Sciences…”
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Investigation of multifilamentary Nb3Sn strand for ITER by internal Sn process by Zhang, P.X., Zhou, L., Tang, X.D., Li, C.G., Wu, Y., Li, K., Yan, G., Yang, M., Feng, Y., Liu, X.H., Weng, P.D., Lu, Y.F.

“…By internal Sn process we have successfully fabricated the multifilamentary Nb3Sn strand with a diameter of 0.79mm, which has 5616–6270 filaments. A two-step…”
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EAST in-vessel components design by Yao, D.M., Li, J.G., Song, Y.T., Du, S.J., Chen, J.L., Weng, P.D.

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

“…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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Development of multifilamentary niobium–titanium and niobium–tin strands for the International Thermonuclear Experimental Reactor project by Zhou, L., Zhang, P.X., Tang, X.D., Liu, X.H., Lu, Y.F., Weng, P.D., Grunblatt, G., Hoang, Gia K., Verwaerde, C.

“…The International Thermonuclear Experimental Reactor(ITER) device should demonstrate the scientific and technological possibility of commercial fusion energy…”
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Effect of twist process on critical current and hysteresis loss of Nb3Sn strands by Zhang, P.X., Zhou, L., Tang, X.D., Liang, M., Li, C.G., Wu, Y., Yan, G., Yang, M., Feng, Y., Liu, X.H., Weng, P.D., Lu, Y.F.

“…We have prepared Nb3Sn strands by the internal tin process for superconducting conductor application in the international thermonuclear experimental reactor…”
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Cryostat engineering design and manufacturing of the EAST superconducting Tokamak by Yu, J., Wu, S.T., Mao, X.Q., Gao, D.M., Weng, P.D., Luo, J.Y., Pei, S.B.

“…EAST cryostat is a large single walled vessel surrounding the entire basic machine consisting of central cylindrical section and two end enclosures, a flat…”
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Prediction of quench in cable-in-conduit conductors considering current-sharing effect of copper by Tan, Y.F., Weng, P.D., Xiao, B.J.

“…A simple 0D analytical model for the prediction of the quench point has been presented by Anghel [Anghel A. A simple model for the prediction of quench point…”
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HT-7U vacuum vessel by Yao, D.M., Song, Y.T., Wu, S.T., Weng, P.D.

“…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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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.

“…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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HT-7U TF and PF conductor design by Weng, P.D, Bi, Y.F, Chen, Z.M, Li, B.Z, Fang, J

“…The HT-7U tokamak is a Chinese National Project. The mission of the project is to build an advanced full superconducting tokamak. NbTi strands are selected as…”
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Structural analyses and preliminary design of HT-7U cryostat by Yu, J., Wu, S.T., Song, Y.T., Weng, P.D.

“…The cryostat of HT-7U Tokamak is a large vacuum vessel surrounding the entire Basic Machine with cylindrical shell, dished top and flat bottom. The main…”
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