Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification

S Brezinsek, JW Coenen, T Schwarz-Selinger… - Nuclear …, 2017 - iopscience.iop.org
The provision of a particle and power exhaust solution which is compatible with first-wall
components and edge-plasma conditions is a key area of present-day fusion research and …

Liquid metals as a divertor plasma-facing material explored using the Pilot-PSI and Magnum-PSI linear devices

TW Morgan, P Rindt, GG Van Eden… - Plasma Physics and …, 2017 - iopscience.iop.org
For DEMO and beyond, liquid metal plasma-facing components are considered due to their
resilience to erosion through flowed replacement, potential for cooling beyond conduction …

Non-contact measurement of thermal diffusivity in ion-implanted nuclear materials

F Hofmann, DR Mason, JK Eliason, AA Maznev… - Scientific reports, 2015 - nature.com
Abstract Knowledge of mechanical and physical property evolution due to irradiation
damage is essential for the development of future fission and fusion reactors. Ion-irradiation …

Recent progress in the design of the K-DEMO divertor

S Kwon, K Im, SH Hong, H Lee, TD Rognlien… - Fusion Engineering and …, 2020 - Elsevier
The preliminary conceptual design of the Korean fusion demonstration reactor (K-DEMO)
with a major radius of 6.8 m and the fusion power of 2200 MW has been studied since 2012 …

[HTML][HTML] Power handling of a liquid-metal based CPS structure under high steady-state heat and particle fluxes

TW Morgan, A Vertkov, K Bystrov, I Lyublinski… - Nuclear Materials and …, 2017 - Elsevier
Liquid metal infused capillary porous structures (CPSs) are considered as a potential
divertor solution for DEMO due to their potential power handling capability and resilience to …

Aiming at understanding thermo-mechanical loads in the first wall of DEMO: stress–strain evolution in a Eurofer-tungsten test component featuring a functionally …

S Heuer, T Weber, G Pintsuk, JW Coenen… - Fusion Engineering and …, 2018 - Elsevier
For the future fusion demonstration power plant, DEMO, several blanket designs are
currently under consideration. Despite geometric and operational differences, all designs …

Mechanical properties and fracture mechanism of CuCrZr alloy and pure Cu at high temperatures by small punch test

X Zhu, J Peng, W Su, X Miao, W Ni, Q Zhang… - Journal of Nuclear …, 2024 - Elsevier
In nuclear power plants, CuCrZr alloy and pure copper (T2) are widely used as the structural
materials and service at high temperatures, and the comprehensive understanding of the …

The development and testing of the thermal break divertor monoblock target design delivering 20 MW m− 2 heat load capability

M Fursdon, T Barrett, F Domptail, LM Evans… - Physica …, 2017 - iopscience.iop.org
The design and development of a novel plasma facing component (for fusion power plants)
is described. The component uses the existing'monoblock'construction which consists of a …

Enhancing the DEMO divertor target by interlayer engineering

TR Barrett, SC McIntosh, M Fursdon, D Hancock… - Fusion Engineering and …, 2015 - Elsevier
A robust water-cooled divertor target plate solution for DEMO has to date remained elusive.
Common to all contemporary concepts is an interlayer at the boundary between the tungsten …

New WC-Cu thermal barriers for fusion applications: High temperature mechanical behaviour

E Tejado, M Dias, JB Correia, T Palacios… - Journal of Nuclear …, 2018 - Elsevier
The combination of tungsten carbide and copper as a thermal barrier could effectively
reduce the thermal mismatch between tungsten and copper alloy, which are proposed as …