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 …

Theory-based scaling laws of near and far scrape-off layer widths in single-null L-mode discharges

M Giacomin, A Stagni, P Ricci, JA Boedo… - Nuclear …, 2021 - iopscience.iop.org
Abstract Theory-based scaling laws of the near and far scrape-off layer (SOL) widths are
analytically derived for L-mode diverted tokamak discharges by using a two-fluid model. The …

Real-time feedback control of the impurity emission front in tokamak divertor plasmas

T Ravensbergen, M van Berkel, A Perek… - Nature …, 2021 - nature.com
In magnetic confinement thermonuclear fusion the exhaust of heat and particles from the
core remains a major challenge. Heat and particles leaving the core are transported via …

Runaway electron experiments at COMPASS in support of the EUROfusion ITER physics research

J Mlynar, O Ficker, E Macusova… - Plasma Physics and …, 2018 - iopscience.iop.org
The role of the COMPASS tokamak in research of generation, confinement and losses of
runaway electron (RE) population is presented. Recently, two major groups of experiments …

Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks

J Horacek, J Adamek, M Komm, J Seidl… - Nuclear …, 2020 - iopscience.iop.org
Scaling of L-mode heat flux for ITER and COMPASS-U divertors, based on five tokamaks -
IOPscience Skip to content IOP Science home Accessibility Help Search Journals Journals list …

Overview of operation and experiments in the ADITYA-U tokamak

RL Tanna, H Raj, J Ghosh, R Kumar, S Aich… - Nuclear …, 2019 - iopscience.iop.org
The first Indian tokamak, ADITYA, operated for over two decades with a circular poloidal
limiter, has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) to attain …

Constraints on conceptual design of diagnostics for the high magnetic field COMPASS-U tokamak with hot walls

V Weinzettl, J Adamek, P Bilkova, J Havlicek… - Fusion Engineering and …, 2019 - Elsevier
COMPASS-U, a high magnetic field tokamak with hot walls, will be designed and built at IPP
Prague. Unique features of this new device bring noticeable constraints and requirements …

Real-time feedback system for divertor heat flux control at COMPASS tokamak

I Khodunov, M Komm, A Havranek… - Plasma Physics and …, 2021 - iopscience.iop.org
The reduction of the incident heat flux onto the divertor will be a necessity for the future
thermonuclear reactors. Impurity seeding is recognized as an efficient way to achieve the …

Development of the diagnostic tools for the COMPASS-U tokamak and plans for the first plasma

V Weinzettl, P Bilkova, I Duran, M Hron, R Panek… - Fusion Engineering and …, 2023 - Elsevier
Abstract The COMPASS-U tokamak (R= 0.894 m, a= 0.27 m, B t= 5 T, I p= 2 MA) is a new
medium-size device with fully metallic plasma facing components, currently under …

Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping

J Horacek, S Lukes, J Adámek, J Havlicek, S Entler… - Scientific Reports, 2022 - nature.com
One of the remaining challenges in magnetic thermonuclear fusion is survival of the heat
shield protecting the tokamak reactor vessel against excessive plasma heat fluxes …