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Nuclear Fusion and Plasma Physics ›› 2021, Vol. 41 ›› Issue (3): 258-263.DOI: 10.16568/j.0254-6086.202103011

• Nuclear Fusion Engineering and Technology • Previous Articles     Next Articles

Structural design of vacuum vessel system of a high heat flux test facility #br#  for divertor components of fusion device

LI Bo, MAO Xin, XU Shu-ling, SHEN Jun-song, YIN Zhou, LI Qiang, WANG Wan-jing, LEI Ming-zhun   

  1. (Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 230031)
  • Received:2020-01-21 Revised:2020-09-01 Online:2021-09-15 Published:2021-09-29

适用于聚变装置偏滤器部件的高热负荷 测试平台真空腔体系统设计

李  波,卯  鑫*,徐淑玲,沈俊松, 尹  洲,李  强,王万景,雷明准   

  1. (中国科学院等离子体物理研究所,合肥 230031)
  • 作者简介:李波(1985−),男,安徽安庆人,学士,助理工程师,主要从事托卡马克相关测试装置设计研究。
  • 基金资助:
    国家重大科技基础设施(CR202002) 

Abstract: The structural design of a high heat flux test facility for divertor components of fusion device, including vacuum vessel, vacuum pumping system, manipulator, small-scale water-cooling system, electronic gun operating platform and so on, is carried out. The rationality and reliability of vacuum vessel structure has been verified through Ansys software. The simulation results show that the max temperature of vacuum vessel outer wall is less than 50℃, and the maximum stresses of vacuum vessel and its support are 134.49MPa and 48.76MPa respectively, meeting the allowable stress intensity requirement (3Sm=620MPa).

Key words: Fusion device, Divertor, High heat flux test facility

摘要: 对托卡马克聚变装置偏滤器的高热负荷测试平台真空腔体系统进行了结构设计,其中包括真空室、 真空抽气系统、部件调节机构、小型水冷系统和电子枪操作平台,利用 Ansys 对真空室主体结构的合理性和可靠 性进行了验证。模拟结果表明:真空室外壁温度不超过 50℃,真空室及其支撑上的最大应力分别为 134.49MPa 和 48.76MPa,满足许用应力 3Sm 值 620MPa 的要求。

关键词:  Fusion device, Divertor, High heat flux test facility

CLC Number: