[HTML][HTML] Status and future development of heating and current drive for the EU DEMO
MQ Tran, P Agostinetti, G Aiello, K Avramidis… - Fusion engineering and …, 2022 - Elsevier
The European DEMO is a pulsed device with pulse length of 2 hours. The functions devoted
to the heating and current drive system are: plasma breakdown, plasma ramp-up to the flat …
to the heating and current drive system are: plasma breakdown, plasma ramp-up to the flat …
Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond
S Coda, M Agostini, R Albanese, S Alberti… - Nuclear …, 2019 - iopscience.iop.org
The research program of the TCV tokamak ranges from conventional to advanced-tokamak
scenarios and alternative divertor configurations, to exploratory plasmas driven by …
scenarios and alternative divertor configurations, to exploratory plasmas driven by …
[HTML][HTML] Overview of the TCV digital real-time plasma control system and its applications
C Galperti, F Felici, T Vu, O Sauter, F Carpanese… - Fusion Engineering and …, 2024 - Elsevier
Real-time plasma control systems are at the heart of operation of modern tokamaks. The
control system of the TCV tokamak has recently seen a major upgrade in terms of its …
control system of the TCV tokamak has recently seen a major upgrade in terms of its …
Confinement properties of L-mode plasmas in ASDEX Upgrade and full-radius predictions of the TGLF transport model
The properties of L-mode confinement have been investigated with a set of dedicated
experiments in ASDEX Upgrade and with a related modelling activity with the transport code …
experiments in ASDEX Upgrade and with a related modelling activity with the transport code …
[HTML][HTML] Quasioptical modeling of wave beams with and without mode conversion. I. Basic theory
IY Dodin, DE Ruiz, K Yanagihara, Y Zhou… - Physics of Plasmas, 2019 - pubs.aip.org
This work opens a series of papers where we develop a general quasi-optical theory for
mode-converting electromagnetic beams in plasma and implement it in a numerical …
mode-converting electromagnetic beams in plasma and implement it in a numerical …
[HTML][HTML] From L-mode to the L–H transition, experiments on ASDEX upgrade and related gyrokinetic simulations
N Bonanomi, C Angioni, GD Conway, T Happel… - Physics of …, 2024 - pubs.aip.org
This work combines experimental observations from the ASDEX Upgrade tokamak with
related gyrokinetic simulations of the turbulence moving from L-mode toward, and beyond …
related gyrokinetic simulations of the turbulence moving from L-mode toward, and beyond …
Quantifying electron cyclotron power deposition broadening in DIII-D and the potential consequences for the ITER EC system
JH Slief, RJR van Kampen, MW Brookman… - Nuclear …, 2023 - iopscience.iop.org
The injection of electron cyclotron (EC) waves fulfills a number of important tasks in nuclear
fusion devices for which detailed knowledge of the spatial power deposition profile is critical …
fusion devices for which detailed knowledge of the spatial power deposition profile is critical …
Simulation of heating and current drive sources for scenarios of the ITER research plan
M Schneider, E Lerche, D Van Eester, O Hoenen… - Nuclear …, 2021 - iopscience.iop.org
Predicting the impact of heating and current drive (H&CD) sources is essential to evaluate
the performance of ITER plasmas and to subsequently optimise the scenarios for the four …
the performance of ITER plasmas and to subsequently optimise the scenarios for the four …
The modeling of a tokamak plasma discharge, from first principles to a flight simulator
E Fable, F Janky, W Treutterer… - Plasma Physics and …, 2022 - iopscience.iop.org
A newly developed tool to simulate a tokamak full discharge is presented. The tokamak'flight
simulator'Fenix couples the tokamak control system with a fast and reduced plasma model …
simulator'Fenix couples the tokamak control system with a fast and reduced plasma model …
First demonstration of real-time kinetic equilibrium reconstruction on TCV by coupling LIUQE and RAPTOR
F Carpanese, F Felici, C Galperti, A Merle… - Nuclear …, 2020 - iopscience.iop.org
Kinetic equilibrium reconstruction (KER) in tokamaks is the solution of the free-boundary
MHD equilibrium that best fits the external magnetic measurements and the internal plasma …
MHD equilibrium that best fits the external magnetic measurements and the internal plasma …