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Perspectives on multiscale modelling and experiments to accelerate materials development for fusion
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 …
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
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 …
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
Continuous advancement in nonvolatile and morphotropic beyond-Moore electronic devices
requires integration of ferroelectric and semiconductor materials. The emergence of hafnium …
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
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 …
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
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 …
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
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 …
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 …
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
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 …
nuclear reactor systems due to their resistance to radiation induced swelling. Cavity and …
Emulation of fast reactor irradiated T91 using dual ion beam irradiation
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° …
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
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 …
angle, low angle and special Σ3 GBs in an Fe-Mn-Si steel has been investigated by using …