Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

A Bhattacharya, SJ Zinkle, J Henry… - Journal of Physics …, 2022 - iopscience.iop.org
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …

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 …

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 …

Ultrahigh strength, thermal stability and high thermal conductivity in hierarchical nanostructured Cu-W alloy

JG Ke, R Liu, ZM **e, LC Zhang, XP Wang, QF Fang… - Acta Materialia, 2024 - Elsevier
The wider application of copper alloys is challenged due to their relatively low strength and
thermal stability. Here we report a nano-reinforcement dispersion strategy to achieved an …

Development of the material property handbook and database of CuCrZr

K Zhang, E Gaganidze, M Gorley - Fusion Engineering and Design, 2019 - Elsevier
This paper covers the initial progress on the development of material property handbook
(MPH) of baseline CuCrZr, within the Materials Engineering Data and Design Integration …

Dislocation dynamics simulation of thermal annealing of a dislocation loop microstructure

A Breidi, SL Dudarev - Journal of Nuclear Materials, 2022 - Elsevier
Thermal evolution and elevated temperature annealing of the dislocation microstructure of
an irradiated metal, represented by an ensemble of elastically interacting interstitial …

Nonuniversal structure of point defects in face-centered cubic metals

PW Ma, SL Dudarev - Physical Review Materials, 2021 - APS
Using ab initio density function theory calculations, we have determined the structure of self-
interstitial atom (SIA) defects in the most commonly occurring face-centered cubic (FCC) …

Effects of swift heavy ions at different fluencies on WC-6Co hard metal alloy

E Demir, E Popov, M Mirzayev, L Slavov, D Neov… - International Journal of …, 2022 - Elsevier
Tungsten carbide hard metal alloy with 6% by weight cobalt was studied before and after
irradiation at different fluencies with 167 MeV 132 Xe ions. Raman spectroscopy, X-ray …

Recent progress in the assessment of irradiation effects for in-vessel fusion materials: tungsten and copper alloys

D Terentyev, M Rieth, G Pintsuk, J Riesch… - Nuclear …, 2022 - iopscience.iop.org
The present contribution highlights results of the recent irradiation campaigns applied to
screen mechanical properties of advanced tungsten and copper-based materials—main …

STEP—on the pathway to fusion commercialization

H Wilson, I Chapman, T Denton, W Morris… - … Fusion Energy: How …, 2020 - iopscience.iop.org
Entering its final construction phase, the international fusion experiment, ITER, will
demonstrate much of the science and technology for net fusion gain. In parallel, major …