Diagnostics for steady state plasmas

HJ Hartfuss, R König, A Werner - Plasma physics and controlled …, 2006 - iopscience.iop.org
Problems related to the development of diagnostics for steady state fusion plasma
experiments are discussed. The paper concentrates on those necessities already appearing …

Overview of KSTAR initial operation

M Kwon, YK Oh, HL Yang, HK Na, YS Kim… - Nuclear …, 2011 - iopscience.iop.org
Since the successful first plasma generation in the middle of 2008, three experimental
campaigns were successfully made for the KSTAR device, accompanied with a necessary …

Magnetic control of plasma current, position, and shape in tokamaks: a survey or modeling and control approaches

G Ambrosino, R Albanese - IEEE Control Systems Magazine, 2005 - ieeexplore.ieee.org
Plasma current, position and shape control systems and modeling approaches were
reviewed. The literature was divided into three categories, namely plasma radial position …

Design features of the KSTAR in-vessel control coils

HK Kim, HL Yang, GH Kim, JY Kim, H Jhang… - Fusion Engineering and …, 2009 - Elsevier
In-vessel control coils (IVCCs) are to be used for the fast plasma position control, field error
correction (FEC), and resistive wall mode (RWM) stabilization for the Korea …

Plasma Control in Tokamaks. Part 2.

YV Mitrishkin, NM Kartsev, EA Pavlova… - Advances in Systems …, 2018 - ijassa.ipu.ru
Various systems of magnetic control of plasma position, current, and shape are considered
in vertically elongated tokamaks including spherical tokamaks being in operation. The …

Plasma magnetic cascade multiloop control system design methodology in a tokamak

YV Mitrishkin, PS Korenev, NM Kartsev… - Control Engineering …, 2019 - Elsevier
The paper treats the methodology of the design and analysis of a tokamak plasma magnetic
cascade multiloop control system with the example of the Globus-M spherical tokamak (Ioffe …

The control system of KSTAR

M Kwon, IS Choi, JW Choi, JS Hong, MC Keum… - Fusion engineering and …, 2004 - Elsevier
The Korea Superconducting Tokamak Advanced Research (KSTAR) is a medium size, fully
superconducting tokamak, which is scheduled to begin operation in year 2006. The control …

Development of KSTAR in-vessel components and heating systems

HL Yang, YM Park, YS Bae, HK Kim, KM Kim… - Fusion engineering and …, 2011 - Elsevier
In-vessel components of the Korea Superconducting Tokamak Advanced Research
(KSTAR) were developed for 2010 campaign to provide a crucial circumstance for achieving …

Identification of the plasma boundary shape and position in the Damavand tokamak

C Rasouli, F Abbasi Davani - Plasma Physics Reports, 2017 - Springer
A series of experiments and numerical calculations have been done on the Damavand
tokamak for accurate determination of equilibrium parameters, such as the plasma boundary …

Development of in-vessel vertical coil power supply in KSTAR

JK Jin, JH Choi, DK Lee, SH Han… - … on Plasma Science, 2013 - ieeexplore.ieee.org
The Korea Superconducting Tokamak Advanced Research (KSTAR) device is an advanced
superconducting tokamak to establish scientific and technological bases for an attractive …