The DEMO wall load challenge

R Wenninger, R Albanese, R Ambrosino… - Nuclear …, 2017 - iopscience.iop.org
For several reasons the challenge to keep the loads to the first wall within engineering limits
is substantially higher in DEMO compared to ITER. Therefore the pre-conceptual design …

[HTML][HTML] Plasma-wall interaction impact of the ITER re-baseline

RA Pitts, A Loarte, T Wauters, M Dubrov… - Nuclear Materials and …, 2024 - Elsevier
To mitigate the impact of technical delays, provide a more rationalized approach to the
safety demonstration and move forward as rapidly as possible to a reactor relevant materials …

The GBS code for tokamak scrape-off layer simulations

FD Halpern, P Ricci, S Jolliet, J Loizu, J Morales… - Journal of …, 2016 - Elsevier
We describe a new version of GBS, a 3D global, flux-driven plasma turbulence code to
simulate the turbulent dynamics in the tokamak scrape-off layer (SOL), superseding the code …

[HTML][HTML] Impact of plasma-wall interaction and exhaust on the EU-DEMO design

F Maviglia, M Siccinio, C Bachmann, W Biel… - Nuclear materials and …, 2021 - Elsevier
In the present work, the role of plasma facing components protection in driving the EU-
DEMO design will be reviewed, focusing on steady-state and, especially, on transients. This …

The ITER project construction status

O Motojima - Nuclear Fusion, 2015 - iopscience.iop.org
The pace of the ITER project in St Paul-lez-Durance, France is accelerating rapidly into its
peak construction phase. With the completion of the B2 slab in August 2014, which will …

Scrape-off layer transport and filament characteristics in high-density tokamak regimes

N Vianello, D Carralero, CK Tsui, V Naulin… - Nuclear …, 2019 - iopscience.iop.org
A detailed cross-device investigation on the role of filamentary dynamics in high-density
regimes has been performed within the EUROfusion framework, comparing the ASDEX …

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 …

Modification of SOL profiles and fluctuations with line-average density and divertor flux expansion in TCV

N Vianello, C Tsui, C Theiler, S Allan, J Boedo… - Nuclear …, 2017 - iopscience.iop.org
A set of Ohmic density ramp experiments addressing the role of parallel connection length in
modifying scrape off layer (SOL) properties has been performed on the TCV tokamak. The …

SMITER: A field-line tracing environment for ITER

L Kos, RA Pitts, G Simič, M Brank, H Anand… - Fusion Engineering and …, 2019 - Elsevier
Built around the SMARDDA modules for magnetic field-line tracing [IEEE Tr. Plasma Sc. 42
(2014) 1932], the SMITER code package (SMARDDA for ITER) is a new graphical user …

Multi-machine scaling of the main SOL parallel heat flux width in tokamak limiter plasmas

J Horacek, RA Pitts, J Adamek, G Arnoux… - Plasma Physics and …, 2016 - iopscience.iop.org
As in many of today's tokamaks, plasma start-up in ITER will be performed in limiter
configuration on either the inner or outer midplane first wall (FW). The massive, beryllium …