SYSTEM DESIGN OF THE CLUSTER TEST FACILITY.

[In Japanese. / En japonais.]

Author(s) : YOSHIDA K.

Type of article: Article

Summary

THIS PAPER DESCRIBES SYSTEM DESIGN OF THE CLUSTER TEST FACILITY (CTF) WHICH IS A TEST FACILITY TO DEVELOP HIGH FIELD TOROIDAL COILS MORE THAN 12 T FOR FUSION REACTOR. THE CTF IS COMPOSED OF TWO CLUSTER TEST COILS (CTC), A 100-L/H HELIUM CRYOGENIC SYSTEM, A VACUUM SYSTEM, A 3 KA DC POWER SUPPLY AND PROTECTION SYSTEM, AND A COMPUTER SYSTEM FOR DATA ACQUISITION AND CONTROL. THE PURPOSE OF THE CTF IS NOT ONLY TO TEST THE TEST MODULE COIL, BUT ALSO TO DEVELOP AND VERIFY TOTAL TECHNOLOGY REQUIRED FOR SUPERCONDUCTING COIL SYSTEM FOR THE TOKAMAK REACTOR AT THE JAPAN ATOMIC ENERGY RESEARCH INSTITUTE.

Details

  • Original title: [In Japanese. / En japonais.]
  • Record ID : 1984-1782
  • Languages: Japanese
  • Source: Cryogenics/ Cryog. Eng. - vol. 19 - n. 2
  • Publication date: 1984
  • Document available for consultation in the library of the IIR headquarters only.

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