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Second Harmonic Breakdown in KSTAR

AIP Conference Proceedings, 2007
An 84‐GHz electron cyclotron heating (ECH) system is being installed on the KSTAR tokamak. KSTAR adopts ECH‐assisted start‐up for the flexibility and reliability of the KSTAR operation with the plasma breakdown voltage reduced. The available maximum power of the 84 GHz ECH system is presently 500 kW with maximum duration of 2 s.
Y. S. Bae   +5 more
openaire   +1 more source

Overview of KSTAR ICRF Experiments

AIP Conference Proceedings, 2011
At magnetic field of 2 T, 30 MHz, 500 kW of RF power was injected for the central ion and electron heating for D(H) plasmas of KSTAR tokamak. Clear evidence of plasma temperature and stored energy elevation were observed with less impurity generation compared to the previous campaign.
S. J. Wang   +6 more
openaire   +1 more source

KSTAR Tokamak Neutronic Analysis

IEEE Conference Record - Abstracts. 2005 IEEE International Conference on Plasma Science, 2005
Summary form only given. KSTAR, which is to develop the construction techniques of a steady-state-capable advanced superconducting tokamak and to establish a scientific and technical basis for an attractive fusion reactor, is under construction in Korea. High-beta, beam-heated KSTAR deuterium plasmas should produce fusion neutrons.
C.-S. Kim, H.-S. Lee, M. Kwon
openaire   +1 more source

Jacketing and Repair of the KSTAR CICC

IEEE Transactions on Appiled Superconductivity, 2005
The KSTAR (Korea Superconducting Tokamak Advanced Research) superconducting magnet system which consists of 16 TF coils and 14 PF coils adopts a superconducting CICC (Cable-In-Conduit Conductor) type conductor. The KSTAR magnet system uses two different types of CICCs-Nb/sub 3/Sn cable with Incoloy 908 conduit and NbTi cable with 316LN stainless-steel ...
B.S. Lim   +14 more
openaire   +1 more source

Key Features in the Operation of KSTAR

IEEE Transactions on Plasma Science, 2012
The Korea Superconducting Tokamak Advanced Research (KSTAR) device is aimed at advanced tokamak (AT) research. Three years have passed since it achieved its first plasma in 2008. Because it is a superconducting machine and is working toward AT research, it has unique features in terms of the machine engineering and operation.
Jong-Gu Kwak   +38 more
openaire   +1 more source

Current status of the KSTAR construction

Cryogenics, 2007
The KSTAR is a superconducting tokamak under construction at the National Fusion Research Center (NFRC) in Daejeon, Korea. The project, of which mission aims at a steady-state operation and advanced tokamak physics, is under peak phase in the fabrication and assembly works.
J.S. Bak   +9 more
openaire   +1 more source

The KSTAR superconducting magnet system

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
The Korean Superconducting Tokamak Advanced Research (KSTAR) at the Korea Basic Science Institute in Taejon will be the first Tokamak with an advanced all superconducting magnet system, including toroidal field (TF), poloidal field (PF),and field error correction (FEC) coils.
J.H. Schultz   +9 more
openaire   +1 more source

Microwave imaging reflectometry for KSTAR

Journal of Instrumentation, 2012
A microwave imaging reflectometry (MIR) system with two probing frequencies is being developed for 2D measurement of electron density fluctuations for KSTAR plasmas. The two-frequency probe beam enables simultaneous measurement of density fluctuations at two cut-off layers.
Lee, W   +10 more
openaire   +2 more sources

Cryogenic system for KSTAR Tokamak

AIP Conference Proceedings, 2002
The Korea Superconducting Tokamak Advanced Research (KSTAR) Project has been in progress since 1996. Major parameters of the KSTAR tokamak are: major radius 1.8 m, minor radius 0.5 m, toroidal field 3.5 Tesla. The KSTAR device has a fully CICC type superconducting coil system.
openaire   +1 more source

Lighting the FIRE in KSTAR Plasmas

The status of Fast Ion Regulated Enhancement (FIRE) mode experiment in KSTAR is presented. This regime is being developed for high-performance, steady-state operation, featuring a stationary ion internal transport barrier that enables central ion temperatures approaching 10 keV to be sustained for up to 50 s without delicate profile control and with no
openaire   +1 more source

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