Commissioning and initial operation of KSTAR superconducting tokamak

Oh, Y.K.; Kim, W.C.; Park, K.R.; Park, M.K.; Yang, H.L.; Kim, Y.S.; Chu, Yong; Bak, J. G.; Baang, E.N.; Yoon, S.W.; Hahn, S. H.; Lee, H.J.; Park, S.H.; Kim, K.H.; Hong, Jaesic; Baek, S.; Kim, M.K.; Lee, T.G.; Lee, S.I.; Bae, Y. S.; Yonekawa, H.; Choi, Jaewon; Hwang, Insung; Cho, K.W.; Park, Y.M.; Kim, J.Y.; Lee, J.H.; Kwon, M.; Lee, G.S.; Kwak, J. G.; Ahn, Hyun-Sik; Walker, M.L.; Humphreys, D.A.; Leuer, J.A.; Hyatt, A.W.; Jackson, G.L.; Mueller, D.; Ivanov, D.P.

doi:10.1016/j.fusengdes.2008.12.099

Cited by 74 publications

(28 citation statements)

References 7 publications

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“…The ion power balance is given by (2) eqn. 2, where P CX is the loss due to charge-exchange and P i con is the heat loss from the ions due to confinement.…”

Section: Additional Requirement For Tokamaks With Superconducting mentioning

confidence: 99%

“…Recent experience on the start-up of the Experimental Advanced Superconducting Tokamak (EAST) 1 , the Korean Superconducting Tokamak Advanced Research (KSTAR) 2 and start-up experiments in the Joint European Torus (JET) 3 with the ITER-like-wall (ILW) 4 provide a perspective for planning for the start-up of the National Spherical Torus Experiment Upgrade (NSTX-U) 5 , the Japan Torus 60-Super Advanced (JT-60SA) 6 and the International Thermonuclear Experimental Reactor (ITER) 7 which will be carried out in the coming years. These devices will rely upon a central solenoid for start-up.…”

Section: Introductionmentioning

confidence: 99%

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The Physics of Tokamak Start-up

Mueller¹

2012

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Tokamak start-up on present-day devices usually relies on inductively induced voltage from a central solenoid. In some cases inductive startup is assisted with auxiliary power from electron cyclotron radio frequency heating.ITER, the National Spherical Torus eXperiment Upgrade and JT60, now under construction, will make use of the understanding gained from present-day devices to ensure successful start-up. Design of a spherical tokamak (ST) with DT capability for nuclear component testing would require an alternative to a central solenoid because the small central column in an ST has insufficient space to provide shielding for the insulators in the solenoid. Alternative start-up techniques such as induction using outer poloidal field coils, electron Bernstein wave start-up, coaxial helicity injection and point source helicity injection have been used with success, but require demonstration of scaling to higher plasma current.

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“…The ion power balance is given by (2) eqn. 2, where P CX is the loss due to charge-exchange and P i con is the heat loss from the ions due to confinement.…”

Section: Additional Requirement For Tokamaks With Superconducting mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

The Physics of Tokamak Start-up

Mueller¹

2012

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“…KSTAR magnet system consists of 16 TF coils and 14 PF coils which are cooled down less than 5 K with helium [1]. In the world, KSTAR is the only operating superconducting tokamak adopting Nb 3 Sn superconductor, so the experimental results are so interesting not only for KSTAR but also ITER even though KSTAR CICC is formed into rectangular shape and has no central hole for helium flow.…”

Section: Kstar Superconducting Magnetmentioning

confidence: 99%

Hydraulic Behaviors of KSTAR PF Coils in Operation

Park¹,

Chu²,

Kim³

et al. 2012

Progress in Superconductivity and Cryogenics

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“…Such disturbances can induce a local temperature rise, eventually leading to quench. To ensure the safe operation of the TF superconducting magnets, the efficient operation of the quench detection system [3] and quench protection system [4] is very important.…”

Section: Introductionmentioning

confidence: 99%

Quench Protection System for the KSTAR Toroidal Field Superconducting Coil

Lee¹,

Choi²,

Jin³

et al. 2012

Journal of Electrical Engineering and Technology

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-The design of the integrated quench protection (QP) system for the high current superconducting magnet (SCM) has been fabricated and tested for the toroidal field (TF) coil system of the Korea Superconducting Tokamak Advanced Research (KSTAR) device. The QP system is capable of protecting the TF SCM, which consists of 16 identical coils serially connected with a stored energy of 495 MJ at the design operation level at 35.2 kA per turn. Given that the power supply for the TF coils can only ramp up and maintain the coil current, the design of the QP system includes two features. The first is a basic fast discharge function to protect the TF SCM by a dump resistor circuit with a 7 s time constant in case of coil quench event. The second is a slow discharge function with a time constant of 360 s for a daily TF discharge or for a stop demand from the tokamak control system. The QP system has been successfully tested up to 40 kA with a short circuit and up to 34 kA with TF SCM in the second campaign of KSTAR. This paper describes the characteristics of the TF QP systems and test results of the plasma experiment of KSTAR in 2009.

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Commissioning and initial operation of KSTAR superconducting tokamak

Cited by 74 publications

References 7 publications

The Physics of Tokamak Start-up

The Physics of Tokamak Start-up

Hydraulic Behaviors of KSTAR PF Coils in Operation

Quench Protection System for the KSTAR Toroidal Field Superconducting Coil

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