Qualification Test Results of the KSTAR Superconducting Coils From the Construction to the Commissioning Steps

Park, K.R.; Chu, Yong; Yonekawa, H.; Baang, E.N.; Kim, Y.O.; Lee, Hyun Jung; Park, Y.M.; Lee, Y.J.; Chang, Hyuk; Lee, D.K.; Choi, Jaehoon; Park, S.H.; Hahn, S.H.; Kim, K.H.; Hwang, Insung; Park, M.K.; Cho, K.W.; Kim, Y.S.; Oh, Y.K.; Bak, J.S.

doi:10.1109/tasc.2009.2018788

Cited by 2 publications

(3 citation statements)

References 6 publications

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“…To ensure the integrity of insulation of the superconducting system after all sub-systems were completely installed, the dc HIPOT test was carried out up to 10 kV in each coil to diagnose the coil insulation before the cool-down. Conclusively, the insulation resistances of all coils were more than 100 M which is the same criterion for the individual coil (Park, K.R. et al, 2009).…”

Section: Inspection At Room Temperaturementioning

confidence: 58%

“…From the measurement, the TF07 coil has the largest flow imbalance among channels, which was about 20%. The averaged values are within approximately 10% (Park, K.R. et al, 2009).…”

Section: Qualification Test Of Superconducting Magnetmentioning

confidence: 72%

“…After finishing the cool-down, the HIPOT test was carried out up to 6 kV for the final insulation check. As the operating currents were lower than the designed ones for all the coils in the first operation, the maximum possible voltage generation is less than 2.5 kV between coil terminals (Park, K.R. et al, 2009).…”

Section: Inspection During and After Cool-downmentioning

confidence: 83%

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Superconductor Application to the Magnetic Fusion Devices for the Steady-State Plasma Confinement Achievement

Oh¹,

Kim²,

Park³

et al. 2012

Superconductors - Properties, Technology, and Applications

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Superconductor Application to the Magnetic Fusion Devices for the Steady-State Plasma Confinement Achievement 363 KSTAR device has lots of technical similarities with the ITER device such as using the same material of superconducting conductor, Nb 3 Sn CICC, and targeting the steady-state high performance plasma confinement over 300s. KSTAR adopted the most outstanding research results from the present devices and will exploit high performance steady-state operation which will provide the core technology for ITER and for future reactors. The designed parameters of KSTAR, as shown in Table 1, are major radius 1.8m, minor radius 0.5 m, toroidal field 3.5 T, and plasma current 2 MA for 300 s. The specific features in the KSTAR design are full superconducting magnets, passive stabilizers and segmented 3-dimentional in-vessel coils for the fast plasma stabilizations, various kinds of heating and current drive systems for the high-beta and non-inductive current drive, and strong plasma shaping for double-null or single-null configurations.

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Section: Inspection At Room Temperaturementioning

confidence: 58%

“…From the measurement, the TF07 coil has the largest flow imbalance among channels, which was about 20%. The averaged values are within approximately 10% (Park, K.R. et al, 2009).…”

Section: Qualification Test Of Superconducting Magnetmentioning

confidence: 72%