[HTML][HTML] Divertor of the European DEMO: Engineering and technologies for power exhaust

JH You, G Mazzone, E Visca, H Greuner… - Fusion Engineering and …, 2022 - Elsevier
In a power plant scale fusion reactor, a huge amount of thermal power produced by the
fusion reaction and external heating must be exhausted through the narrow area of the …

Overview of the DEMO staged design approach in Europe

G Federici, C Bachmann, L Barucca, C Baylard… - Nuclear …, 2019 - iopscience.iop.org
This paper describes the status of the pre-conceptual design activities in Europe to advance
the technical basis of the design of a DEMOnstration Fusion Power Plant (DEMO) to come in …

[HTML][HTML] Development of the plasma scenario for EU-DEMO: Status and plans

M Siccinio, JP Graves, R Kembleton, H Lux… - Fusion Engineering and …, 2022 - Elsevier
This paper is part of a series of publications concerning the development of the European
DEMO during the Pre-Concept Design Phase (2014-2020), and also describing the strategy …

Compact radiative divertor experiments at ASDEX Upgrade and their consequences for a reactor

T Lunt, M Bernert, D Brida, P David, M Faitsch, O Pan… - Physical Review Letters, 2023 - APS
We present a novel concept to tackle the power exhaust challenge of a magnetically
confined fusion plasma. It relies on the prior establishment of an X-point radiator that …

[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 …

Multi-machine SOLPS-ITER comparison of impurity seeded H-mode radiative divertor regimes with metal walls

V Rozhansky, E Kaveeva, I Senichenkov… - Nuclear …, 2021 - iopscience.iop.org
SOLPS-ITER modelling databases of three tokamaks—ASDEX-Upgrade, JET and ITER with
fluid drifts activated are compared to understand the dependence of edge plasma …

[HTML][HTML] Preliminary analysis of alternative divertors for DEMO

F Militello, L Aho-Mantila, R Ambrosino, T Body… - Nuclear Materials and …, 2021 - Elsevier
A physics and engineering analysis of alternative divertor configurations is carried out by
examining benefits and problems by comparing the baseline single null solution with a …

In-situ TEM investigation of nano-scale helium bubble evolution in tantalum-doped tungsten at 800° C

I Ipatova, G Greaves, S Pacheco-Gutiérrez… - Journal of Nuclear …, 2021 - Elsevier
The aim of this work is to probe the helium-induced defect production and accumulation in
40 keV He+ irradiated polycrystalline W and its alternative alloy W-5wt.% Ta using …

[HTML][HTML] Design of a multi-configurations divertor for the DTT facility

P Innocente, R Ambrosino, S Brezinsek… - Nuclear Materials and …, 2022 - Elsevier
The standard positive triangularity H-mode tokamak operation with Single Null Divertor
(SND) configuration and tungsten monoblocks targets can face some difficulties in providing …

Overview of the TCV tokamak experimental programme

H Reimerdes, M Agostini, E Alessi, S Alberti… - Nuclear …, 2022 - iopscience.iop.org
The tokamak à configuration variable (TCV) continues to leverage its unique shaping
capabilities, flexible heating systems and modern control system to address critical issues in …