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Design of the Cryostat for HT-7U Superconducting Tokamak

Design of the Cryostat for HT-7U Superconducting Tokamak
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摘要 The cryostat of HT-7U tokamak is a large vacuum vessel surrounding the entirebasic machine with a cylindrical shell, a dished top and a flat bottom. The main function ofHT-7U cryostat is to provide a thermal barrier between an ambient temperature test hall and aliquid helium-cooled superconducting magnet. The loads applied to the cryostat are from sourcesof vacuum pressure, dead weight, seismic events and electromagnetic forces originated by eddycurrents. It also provides feed-through penetrations for all the connecting elements inside andoutside the cryostat. The main material selected for the cryostat is stainless steel 304L. Thestructural analyses including buckling for the cryostat vessel under the plasma operation conditionhave been carried out by using a finite element code. Stress analysis results show that the maximumstress intensity was below the allowable value. In this paper, the structural analyses and designof HT-7U cryostat are emphasized. The cryostat of HT-7U tokamak is a large vacuum vessel surrounding the entire basic machine with a cylindrical shell, a dished top and a flat bottom. The main function of HT-7U cryostat is to provide a thermal barrier between an ambient temperature test hall and a liquid helium-cooled superconducting magnet. The loads applied to the cryostat are from sources of vacuum pressure, dead weight, seismic events and electromagnetic forces originated by eddy currents. It also provides feed-through penetrations for all the connecting elements inside and outside the cryostat. The main material selected for the cryostat is stainless steel 304L. The structural analyses including buckling for the cryostat vessel under the plasma operation condition have been carried out by using a finite element code. Stress analysis results show that the maximum stress intensity was below the allowable value. In this paper, the structural analyses and design of HT-7U cryostat are emphasized.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2002年第3期1297-1304,共8页 等离子体科学和技术(英文版)
基金 This work was supported by National Meg-Science Engineering Project of Chinese Government.
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参考文献8

  • 1WU S.T., WENG P.D. , "The Project of HT 7U and its Progress", MT-15, Oct., China,1(1997)381-384 .
  • 2WU S.T. , "The Modifications and Requirements of the HT-7U Tokamak Device Design", ASIPP Report, Sept. (1999).
  • 3WANG J., YAO D. M.,YU J., WU S.T., PAN Y.N., WU W.Y., et al., Proc. Fusion Technology 2(1998) 1741-1744.
  • 4WAN Y. X., HT-7 Team, HT-7U Team, Nuclear Fusion 40(6) (2000) 1057-1068.
  • 5YU J., WU S.T., Proc.of HT-7U Device Design 4(2001)188-193 (in Chinese).
  • 6SONG Y.T., YAO D.M., WU S.T. and WENG P.D., Plasma Science & Technology 2(5)(2000)443-448.
  • 7YU J., WU S.T., Proc. Of HT-7U Device Design 4(2001)194-198 (in Chinese).
  • 8DU S.J., "Electrical Parameters of Cryostat in HT-7U Tokamak", ASIPP Report, (1999).

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