Materials for sustainable nuclear energy: a European strategic research and innovation agenda for all reactor generations

L Malerba, A Al Mazouzi, M Bertolus, M Cologna… - Energies, 2022 - mdpi.com
Nuclear energy is presently the single major low-carbon electricity source in Europe and is
overall expected to maintain (perhaps eventually even increase) its current installed power …

Advancements in designing the demo driver blanket system at the EU demo pre-conceptual design phase: overview, challenges and opportunities

FA Hernández, P Arena, LV Boccaccini… - Journal of Nuclear …, 2023 - mdpi.com
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor
(DEMO) during 2014–2020 under the framework of the EUROfusion consortium. The current …

Corrosion behavior of the FeCrAl coating with different Cr and Al contents before and after Au-ions irradiation in stagnant LBE

W Zhang, J Deng, H Yue, S Hu, X Qiu, H Yin, Q Li… - Corrosion …, 2023 - Elsevier
The corrosion behavior of the FeCrAl coating with different Cr and Al contents before and
after Au-ions irradiation was investigated in static LBE. The grain of the irradiated coating …

[HTML][HTML] Effect of Au-ions irradiation on microstructure and mechanical properties of FeCrAl coating

W Zhang, J Deng, H Yin, Y Zhao, X Qiu, M Zhou… - Journal of Materials …, 2023 - Elsevier
Six kinds of FeCrAl coatings with different Cr and Al contents were irradiated by 6 MeV Au-
ions with a damage level of 20 dpa. The results showed that the surface roughness and …

Aspects of applied chemistry related to future goals of safety and efficiency in materials development for nuclear energy

F Golgovici, AE Tudose, D Diniasi, R Nartita, M Fulger… - Molecules, 2023 - mdpi.com
The present paper is a narrative review focused on a few important aspects and moments of
trends surrounding materials and methods in sustainable nuclear energy, as an expression …

Liquid metal cooled fast reactor thermal hydraulic research development: A review

KT Agbevanu, SK Debrah, EM Arthur, E Shitsi - Heliyon, 2023 - cell.com
The growing interest in fast reactors demands further innovative technologies to enhance
their safety and reliability. Understanding thermal hydraulic activities required for advanced …

A novel Ansys CFX–RELAP5 coupling tool for the transient thermal-hydraulic analysis of liquid metal systems

PC Puviani, T Del Moro, B Gonfiotti, D Martelli… - Progress in Nuclear …, 2025 - Elsevier
Thermal-hydraulic analysis of three-dimensional systems and phenomena is essential for
the design and safety assessment of new Generation IV reactor concepts. While System …

[HTML][HTML] Structural and electronic characterization of Pb adsorption on clean and Cr or Ni doped Fe (1 0 0) surface: An ab-initio study

S Giusepponi, F Buonocore, B Ferrucci, M Celino - Surface Science, 2024 - Elsevier
Using ab-initio calculations, the interaction of lead adatom on both the clean and doped iron
(100) surfaces has been investigated. The adsorption energies show that the hollow site …

Deuterium transport behavior of 15-15Ti stainless steel for nuclear structural material in Gen-IV reactors

H Yang, Z Zeng, Z Shao, C Cui, L Xu, Q Lu - International Journal of …, 2024 - Elsevier
As a new type of nuclear reactor, the Gen-IV reactor attracts increasing interest from the
industry. Tritium is produced in lead-cooled fast reactors (LFR), sodium-cooled fast reactor …

Microstructure response and LBE corrosion behavior of the FeCrAlY coating after Au-ions irradiation

W Zhang, J Deng, Y Zhong, H Liu, Z Long, R Wang… - Corrosion …, 2024 - Elsevier
The microstructure and LBE corrosion behavior of the irradiated (up to 110 dpa)
Fe15Cr11Al0. 5Y coatings were investigated. The surface roughness and hardness …