The KSTAR tokamak

The KSTAR tokamak

The KSTAR (Korea Superconducting Tokamak Advanced Research) project is the major effort of the Korean National Fusion Program to design, construct, and operate a steady-state-capable superconducting tokamak. The project is led by Korea Basic Science Institute and shared by national laboratories, uni...

Ausführliche Beschreibung

Gespeichert in:
Bibliographische Detailangaben
Hauptverfasser: Choi, D.I., Lee, G.S., Jinchoon Kim, Park, H.K., Chang, C.S., Choi, B.H., Kim, K., Cho, M.H., Neilson, G.H., Baang, S., Bernabei, S., Brown, T., Chang, H.Y., Cho, C.H., Cho, S., Cho, Y.S., Chung, K.H., Kie-Hyung Chung, Dahlgren, F., Grisham, L., Han, J.H., Huh, N.I., Hwang, S.M., Hwang, Y.S., Hill, D., Hong, B.G., Hong, J.S., Hong, S.H., Im, K.H., In, S.R., Jardin, S., Jhang, H.G., Joo, M., Jung, Y.S., Kessel, C., Kim, D.L., Kim, K.S., Kim, J.Y., Kim, W.C., Kyum, M.C., Lee, D.Y., Lee, B.Y., Lee, D.K., Lee, S.G., Lim, J.Y., Manickam, J., Montgomery, B., Namkung, W., Nevins, W., Oh, Y.K., Park, J.H., Pomphrey, N., Reiersen, W., Schultz, J.H., Schmidt, J.A., Simmons, R.T., Sinnis, J.C., Swain, D.W., Sevier, L., Wang, P.W., Yang, J.G., You, G.H., Yoon, B.J., Young, K.M.
Format: Tagungsbericht
Sprache:eng
Schlagworte:
Educational institutions
Heating
International collaboration
Laboratories
Plasma applications
Plasma devices
Steady-state
Superconducting coils
Superconducting magnets
Tokamaks
Online-Zugang:Volltext bestellen
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Beschreibung
Zusammenfassung:The KSTAR (Korea Superconducting Tokamak Advanced Research) project is the major effort of the Korean National Fusion Program to design, construct, and operate a steady-state-capable superconducting tokamak. The project is led by Korea Basic Science Institute and shared by national laboratories, universities, and industry along with international collaboration. It is in the conceptual design phase and aims for the first plasma by mid 2002. The key design features of KSTAR are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 T, plasma current 2 MA, and flexible plasma shaping (elongation 2.0; triangularity 0.8; double-null poloidal divertor). Both the toroidal and the poloidal field magnets are superconducting coils. The device is configured to be initially capable of 20 s pulse operation and then to be upgraded for operation up to 300 s with non-inductive current drive. The auxiliary heating and current drive system consists of neutral beam, ICRF, lower hybrid, and ECRF. Deuterium operation is planned with a full radiation shielding.
DOI:10.1109/FUSION.1997.687023