Materials to be used in future magnetic confinement fusion reactors: a review

R Alba, R Iglesias, MÁ Cerdeira - Materials, 2022 - mdpi.com
This paper presents the roadmap of the main materials to be used for ITER and DEMO class
reactors as well as an overview of the most relevant innovations that have been made in …

The IFMIF-DONES project: design status and main achievements within the EUROfusion FP8 work programme

D Bernardi, A Ibarra, F Arbeiter, F Arranz… - Journal of Fusion …, 2022 - Springer
Abstract International Fusion Materials Irradiation Facility-DEMO-Oriented NEutron Source
(IFMIF-DONES) is a high-intensity neutron irradiation facility for qualification of fusion reactor …

[HTML][HTML] The IFMIF-DONES project: preliminary engineering design

A Ibarra, F Arbeiter, D Bernardi, M Cappelli… - Nuclear …, 2018 - iopscience.iop.org
The need of a neutron source for the qualification of materials to be used in future fusion
power reactors has been recognized in the European Union (EU) fusion programme for …

Ductile to brittle transition temperature of advanced tungsten alloys for nuclear fusion applications deduced by miniaturized three-point bending tests

C Yin, D Terentyev, T Zhang, S Nogami… - International Journal of …, 2021 - Elsevier
A large campaign of characterization of the ductile to brittle transition temperature (DBTT)
and microstructure has been performed on several commercial and lab-scale pure tungsten …

European materials development: Results and perspective

G Pintsuk, E Diegele, SL Dudarev, M Gorley… - Fusion Engineering and …, 2019 - Elsevier
This paper addresses the EUROfusion DEMO materials research program and highlights
the characterization of the in-vessel baseline materials EUROFER97, CuCrZr and tungsten …

Comprehensive screening of plasma-facing Materials for nuclear fusion

A Fedrigucci, N Marzari, P Ricci - PRX Energy, 2024 - APS
Plasma-facing materials (PFMs) represent one of the most significant challenges for the
design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the …

On the equivalence of irradiation conditions on present and future facilities for fusion materials research and qualification: A computational study

N Castin, D Terentyev, A Bakaev, A Stankovskiy… - Journal of Nuclear …, 2022 - Elsevier
We performed a computational study to assess the suitability and equivalence of the
irradiation conditions on several test irradiation facilities (either currently operating or …

Application of sub-miniaturized bending tests to extract tensile properties from neutron-irradiated metallic alloys

A Bakaev, D Terentyev, A Zinovev, CC Chang… - Journal of Nuclear …, 2022 - Elsevier
In this work, we demonstrate the applicability of sub-miniaturized three-point bending (3PB)
testing for the extraction of tensile plastic properties of metallic materials, such as yield stress …

Potential use of IFMIF-DONES target back-plate for material specimens

Y Qiu, F Arbeiter, D Bernardi, M Frisoni… - Journal of Nuclear …, 2022 - mdpi.com
In the IFMIF-DONES facility of the future, the back-plate behind the Li target will receive
strong irradiation from high-energy neutrons. The potential use of the back-plate for material …

[HTML][HTML] The EUROfusion materials property handbook for DEMO in-vessel components—Status and the challenge to improve confidence level for engineering data

M Gorley, E Diegele, E Gaganidze, F Gillemot… - Fusion Engineering and …, 2020 - Elsevier
The development of a specific materials database and handbook, for engineering design of
in-vessel components of EU-DEMO, is an essential requirement for assessing the structural …