Integrated modeling applications for tokamak experiments with OMFIT
One modeling framework for integrated tasks (OMFIT) is a comprehensive integrated
modeling framework which has been developed to enable physics codes to interact in …
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 …
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 …
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 …
(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 …
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 …
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 …
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
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 …
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 …
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
Abstract Korea Superconducting Tokamak Advanced Research (KSTAR) program is
strongly focused on solving the scientific and technological issues in steady-state high …
strongly focused on solving the scientific and technological issues in steady-state high …