Thermal and Mechanical Analysis of a U-Neck Vacuum Barrier
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  • 作者:Zhongwei Wang ; Yuntao Song ; Kun Lu ; Tingzhi Zhou ; Kaizhong Ding&#8230
  • 关键词:Thermal and mechanical analysis ; ANSYS ; Vacuum barrier
  • 刊名:Journal of Fusion Energy
  • 出版年:2015
  • 出版时间:August 2015
  • 年:2015
  • 卷:34
  • 期:4
  • 页码:827-832
  • 全文大小:1,447 KB
  • 参考文献:1.A. Sagara, O. Mitarai, S. Imagawa, et al., Conceptual design activities and key issues on LHD-type reactor FFHR, in Proceedings of the 15th International Toki Conference on 鈥淔usion and Advanced Technology鈥? vol 11 (2006)
    2.C. Beidler, G. Grieger, E. Harmeyer, et al., Reactor studies on advanced stellarators, in 14th International Conference on Plasma Physics and Control, Fusion Research (1992)
    3.F. Najmabadi, A.R. Raffray, S.I. Abdei-Khalik, et al., The ARIES-CS compact stellarator fusion power plant. Fusion Sci. Technol. 54(3), 655鈥?72 (2008)
    4.F. Najmabadi, The ARIES Team, The ARIES-AT advanced tokamak, advanced technology fusion power plant, ARIES-AT special issue (2006)
    5.F. Najmabadi, C.G. Bathke, M.C. Billone, et al., Overview of the ARIES-RS reversed-shear tokamak power plant study. Fusion Eng. Des. 38(1鈥?), 3鈥?5 (1997)View Article
    6.D. Maisonnier, L. Cook, S. Pierre, et al., DEMO and fusion power plant conceptual studies in Europe. Fusion Eng. Des. 81(8鈥?4), 1123鈥?130 (2006)View Article
    7.K. Tobita, S. Nishio, M. Enoeda, et al., Design study of fusion DEMO plant at JAERI. Fusion Eng. Des. 81(8鈥?4), 1151鈥?158 (2006)View Article
    8.K. Okano, Y. Asaoka, T. Yoshida, et al., Compact reversed shear tokamak reactor with a superheated steam cycle. Nucl. Fusion 40, 635 (2000)ADS View Article
    9.K. Kim, H.C. Kim, S. Oh, et al., A preliminary conceptual design study for Korean fusion DEMO reactor. Fusion Eng. Des. 88(6鈥?), 488鈥?91 (2013)View Article
    10.R. Srinivasan, S.P. Dashpande, The Indian DEMO team, Strategy for the Indian DEMO design. Fusion Eng. Des. 83(7鈥?), 889鈥?92 (2008)View Article
    11.Y. Song et al., Design of the ITER TF magnet feeder systems. Appl. Supercond. 20(3), 1710鈥?713 (2010)ADS View Article
    12.T. Zhou, Y. Song, Design of ITER TF magnet cryostat feeder through, in 18th International Conference on Nuclear Engineering, vol 6 (2010)
    13.K. Lu, T. Zhou, GA CSM feeder system design, Final Design Review presentation (2014)
  • 作者单位:Zhongwei Wang (1)
    Yuntao Song (1)
    Kun Lu (1)
    Tingzhi Zhou (1)
    Kaizhong Ding (1)
    Xiaojun Ni (1)

    1. Institute of Plasma Physics, Chinese Academy of Science, Hefei, China
  • 刊物类别:Engineering
  • 刊物主题:Nuclear Engineering
  • 出版者:Springer Netherlands
  • ISSN:1572-9591
文摘
A vacuum barrier is necessary in the superconducting tokamak, to separate the high reliability main cryostat from the vacuum environments of other systems, like the cryogenic system, which is easier to leak due to the numerous openings for the control and safety valves. Because the vacuum barrier must have a separate plate between the two vacuum environments, all the cryogenic pipelines have to get through the plate with proper sealing, so there is a direct connection from the cryogenic pipeline to the outer duct, that is exposed to the atmosphere and at room temperature. Therefore, the heat load through the vacuum barrier to the cryogenic system must be carefully dealt with. Meanwhile, the vacuum barrier may face a pressure difference between the two sides in some cases, like a leakage accident, so the vacuum barrier should withstand this situation. This paper describes the thermal and mechanical analysis of a U-neck vacuum barrier, which is good at reducting the heat load to the cryogenic system, and is capable to resist the pressure from one side.

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