Integrated modeling applications for tokamak experiments with OMFIT

O Meneghini, SP Smith, LL Lao, O Izacard… - Nuclear …, 2015 - iopscience.iop.org
One modeling framework for integrated tasks (OMFIT) is a comprehensive integrated
modeling framework which has been developed to enable physics codes to interact in …

[PDF][PDF] ASTRA. Automated system for transport analysis in a tokamak

GV Pereverzev, PN Yushmanov - 2002 - pure.mpg.de
Boundary conditions for densities and temperatures Boundary condition for the poloidal flux
3.10. 1 Prescribed plasma current 3. 10.2 Prescribed loop voltage 3.10. 3 External circuit …

Plasma rotation profile measurements using Doppler reflectometry

GD Conway, J Schirmer, S Klenge… - Plasma Physics and …, 2004 - iopscience.iop.org
High spatial resolution radial profiles of the perpendicular plasma rotation velocity u⊥ using
a dual channel 50–75 GHz Doppler reflectometer system on the ASDEX Upgrade tokamak …

Advances in the physics basis for the European DEMO design

R Wenninger, F Arbeiter, J Aubert, L Aho-Mantila… - Nuclear …, 2015 - iopscience.iop.org
In the European fusion roadmap, ITER is followed by a demonstration fusion power reactor
(DEMO), for which a conceptual design is under development. This paper reports the first …

Preliminary design of the COMPASS upgrade tokamak

P Vondracek, R Pánek, M Hron, J Havlicek… - Fusion Engineering and …, 2021 - Elsevier
COMPASS Upgrade is a new medium size, high magnetic field tokamak (R= 0.9 m, B t= 5 T,
I p= 2 MA) currently under design in the Czech Republic. It will provide unique capabilities …

Electron cyclotron heating for W7-X: physics and technology

V Erckmann, P Brand, H Braune… - Fusion science and …, 2007 - Taylor & Francis
The Wendelstein 7X (W7-X) stellarator (R= 5.5 m, a= 0.55 m, B< 3.0 T), which at present is
being built at Max-Planck-Institut für Plasmaphysik, Greifswald, aims at demonstrating the …

Integrated modeling of ASDEX Upgrade plasmas combining core, pedestal and scrape-off layer physics

T Luda, C Angioni, MG Dunne, E Fable… - Nuclear …, 2020 - iopscience.iop.org
The design of future fusion reactors and their operational scenarios requires an accurate
prediction of the plasma confinement. We have developed a new model that integrates …

TORBEAM 2.0, a paraxial beam tracing code for electron-cyclotron beams in fusion plasmas for extended physics applications

E Poli, A Bock, M Lochbrunner, O Maj, M Reich… - Computer Physics …, 2018 - Elsevier
The paraxial WKB code TORBEAM (Poli, 2001) is widely used for the description of electron-
cyclotron waves in fusion plasmas, retaining diffraction effects through the solution of a set of …

Ray-tracing code TRAVIS for ECR heating, EC current drive and ECE diagnostic

NB Marushchenko, Y Turkin, H Maaßberg - Computer Physics …, 2014 - Elsevier
A description of the recently developed ray-tracing code TRAVIS is given together with the
theoretical background, results of benchmarking and examples of application. The code is …

Progress of the KSTAR research program exploring the advanced high performance and steady-state plasma operations

YK Oh, S Yoon, YM Jeon, WH Ko, SH Hong… - Journal of the Korean …, 2018 - Springer
Abstract Korea Superconducting Tokamak Advanced Research (KSTAR) program is
strongly focused on solving the scientific and technological issues in steady-state high …