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Design of Tokamak ELM Coil Support in High Nuclear Heat Environment 被引量:1

Design of Tokamak ELM Coil Support in High Nuclear Heat Environment
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摘要 In Tokomak, the support of the ELM coil, which is close to the plasma and subject to high radiation level, high temperature and high magnetic field, is used to transport and bear the thermal load due to thermal expansion and the alternating electromagnetic force generated by high magnetic field and AC current in the coil. According to the feature of ITER ELM coil, the mechanical performance of rigid and flexible supports under different high nuclear heat levels is studied. Results show that flexible supports have more excellent performance in high nuclear heat condition than rigid supports. Concerning thermal and electromagnetic (EM) loads, optimized results further prove that flexible supports have better mechanical performance than rigid ones. Through these studies, reasonable support design can be provided for the ELM coils or similar coils in Tokamak based on the nuclear heat level. In Tokomak, the support of the ELM coil, which is close to the plasma and subject to high radiation level, high temperature and high magnetic field, is used to transport and bear the thermal load due to thermal expansion and the alternating electromagnetic force generated by high magnetic field and AC current in the coil. According to the feature of ITER ELM coil, the mechanical performance of rigid and flexible supports under different high nuclear heat levels is studied. Results show that flexible supports have more excellent performance in high nuclear heat condition than rigid supports. Concerning thermal and electromagnetic (EM) loads, optimized results further prove that flexible supports have better mechanical performance than rigid ones. Through these studies, reasonable support design can be provided for the ELM coils or similar coils in Tokamak based on the nuclear heat level.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2014年第3期300-304,共5页 等离子体科学和技术(英文版)
关键词 tokomak ELM coil rigid support flexible support high nuclear heat tokomak, ELM coil, rigid support, flexible support, high nuclear heat
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参考文献14

  • 1Du S, Liu X. 2008, Fusion Engineering and Design, 83: 766.
  • 2Heitzenroeder P J, Brooks A W, Chrzanowski J H, et al. 2009, An overview of the iter in-vessel coil systems. 23rd IEEE/NPSS Symposium on Fusion Engineering, San Diego.
  • 3Kalish M, Heitzenroeder P, Brooks A, et al. 2011, Iter In-Vessel Coil design and R&=D. 24th IEEE/NPSS Symposium on Fusion Engineering, Chicago.
  • 4Kim H K, Yang H L, Kim G H, et al. 2009, -hsion Engineering and Design, 84:1029.
  • 5Nardon E, Kirk A, Ben Ayed N, et al. 2009, Journal of Nuclear Materials, 390:773.
  • 6Suttrop W, Gruber O, Gtlnter S, et al. 2009, Fusion Engineering and Design, 84:290.
  • 7JET ELM Coil Study Team. 2010, JET ELM Control Coil Feasibility Study Final Report, JET ELM Coil Study Team.
  • 8Zatz I J, Baker R, Brooks A, et al. 2011, Fusion Engi- neering and Design, 86:1980.
  • 9Bohm T, Brooks A, Bryant L, et al. 2011, Final Re- port On the Preliminary Design of the ITER In-Vessel Coil System. PPPL, Princeton.
  • 10Hong Y S, Ahn H J, Kwon T H, et al. 2011, Fsion Engineering and Design, 86:2021.

同被引文献4

  • 1Heitzenroeder P J, Brooks A W, Chrzanowski J H, et al.An overview of the ITER in-vessel coil systems [C].Symposium on Fusion Engineering, 2009: K.
  • 2Kalish M, Heitzenroeder P, Brooks A. ITER in-vessel coildesign and R&D fC], Symposium on Fusion Engineering,2011; 1-6.
  • 3Zhang S W,Song Y T, Wang Z W, et al. Design study ofsupport for ITER ELM coils [J]. Journal of FusionEnergy, 2014,33: 252-257.
  • 4吴森,赵东标,汪勇.有三个等椭圆孔无限大平板不同受载应力集屮的有限元分析[J].南京航空学院学报,1988,20(2): 42-50.

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