Perspectives on multiscale modelling and experiments to accelerate materials development for fusion

MR Gilbert, K Arakawa, Z Bergstrom, MJ Caturla… - Journal of Nuclear …, 2021‏ - Elsevier
Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …

How Temperature Affects the Selectivity of the Electrochemical CO2 Reduction on Copper

RE Vos, KE Kolmeijer, TS Jacobs, W van der Stam… - ACS …, 2023‏ - ACS Publications
Copper is a unique catalyst for the electrochemical CO2 reduction reaction (CO2RR) as it
can produce multi-carbon products, such as ethylene and propanol. As practical …

Highly enhanced ferroelectricity in HfO2-based ferroelectric thin film by light ion bombardment

S Kang, WS Jang, AN Morozovska, O Kwon, Y **… - Science, 2022‏ - science.org
Continuous advancement in nonvolatile and morphotropic beyond-Moore electronic devices
requires integration of ferroelectric and semiconductor materials. The emergence of hafnium …

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 …

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys

YR Lin, A Bhattacharya, D Chen, JJ Kai, J Henry… - Acta Materialia, 2021‏ - Elsevier
Fe-Cr ferritic-martensitic (FM) steels are promising structural material candidates for fusion
and advanced fission reactors due to their attractive mechanical properties and volumetric …

Comparison of hardening and microstructures of ferritic/martensitic steels irradiated with fast neutrons and dual ions

P Zhu, YR Lin, S Agarwal, V Pauly, S Taller… - Journal of Nuclear …, 2024‏ - Elsevier
Ferritic/martensitic steels T91 and HT9 were irradiated with neutrons (BOR-60 reactor) and
dual ions (9 MeV Fe 3+ and 3.42 MeV energy degraded He 2+) from 369 to 520° C and …

Cavity swelling in irradiated materials

A Bhattacharya, SJ Zinkle - 2020‏ - osti.gov
Cavity swelling, due to three-dimensional clustering of vacancies, is an undesirable isotropic
volume expansion of materials under irradiation. This phenomenon occurs above stage-III …

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments

S Taller, GS Was - Acta Materialia, 2020‏ - Elsevier
Ferritic-martensitic steels are attractive candidates for structural materials in next generation
nuclear reactor systems due to their resistance to radiation induced swelling. Cavity and …

Emulation of fast reactor irradiated T91 using dual ion beam irradiation

S Taller, Z Jiao, K Field, GS Was - Journal of Nuclear Materials, 2019‏ - Elsevier
Dual ion irradiations using 5 MeV defocused Fe 2+ ions and co-injected He 2+ ions were
conducted on a ferritic-martensitic steel alloy, T91, in the temperature range of 406° C–570° …

Irradiation-induced segregation/desegregation at grain boundaries of a ferritic Fe-Mn-Si steel

Q Chen, R Hu, S **, F Xue, G Sha - Acta Materialia, 2021‏ - Elsevier
Irradiation-induced segregation of solutes at typical grain boundaries (GBs) ie random high-
angle, low angle and special Σ3 GBs in an Fe-Mn-Si steel has been investigated by using …