KSTAR TOKAMAK을 위한 저온시스템의 설계

The Design of Cryogenic System for KSTAR TOKAMAK

  • 김동락 (한국기초과학지원연구원) ;
  • 오영국 (한국기초과학지원연구원) ;
  • 정영수 (한국기초과학지원연구원) ;
  • 이정민 (한국기초과학지원연구원) ;
  • 최창호 (한국기초과학지원연구원) ;
  • 임기학 (한국기초과학지원연구원) ;
  • 허남일 (한국기초과학지원연구원) ;
  • 김양수 (한국기초과학지원연구원) ;
  • 박영민 (한국기초과학지원연구원)
  • 발행 : 2001.02.01

초록

Cryogenic technology is one of the key technologies for fusion reactor equipped with superconducting coil for plasma confinement. The KSTAR(Korea Superconducting Tokamak Advanced Research)Project is in progress since 1996. Major parameters of the KSTAR tokamak are : major radius 1.8m, minor radius 0.5m, toroidal field 3.5 Tesla and plasma current 2MA with a strongly shaped plasma cross-section and double -null diverter. Considering practical engineering constraints, the KSTAR device is designed for a pulse length of 300 sec in up-graded operation mode but in the initial configuration would provide a pulse length of 20 sec provided by the poloidal coil system in base-line operation mode. The cryogenic system is composed as follows : cold box, helium compressor system, distribution box, helium gas buffer tank, helium gas purifying system, gas recovery system, liquid helium storage dewar, current lead box, current bus line and liquid nitrogen storage tank.

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