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 …

Effects of radiation-induced defects on corrosion

F Schmidt, P Hosemann, RO Scarlat… - Annual Review of …, 2021 - annualreviews.org
The next generation of nuclear reactors will expose materials to conditions that, in some
cases, are even more extreme than those in current fission reactors, inevitably leading to …

Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

SJ Zinkle, LL Snead - Scripta Materialia, 2018 - Elsevier
Ion beams are indispensible for understanding radiation effects in materials, enabling
access to conditions challenging to perform with neutrons. However, ion irradiations can …

Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels

M Song, M Wang, X Lou, RB Rebak, GS Was - Journal of Nuclear Materials, 2019 - Elsevier
The irradiation-induced microstructure and irradiation-assisted stress corrosion cracking
(IASCC) behavior of additively manufactured (AM) 316L stainless steels produced by laser …

Determination of gamma radiation shielding efficiency by radiation-resistant composite ZrO2–Al2O3–TiO2–WO3–Nb2O5 ceramics

KK Kadyrzhanov, AA Kozlovskiy, M Konuhova… - Optical Materials, 2024 - Elsevier
This work examines the prospects of using composite ZrO 2–Al 2 O 3–TiO 2–WO 3–Nb 2 O 5
ceramics as shielding and radiation-resistant materials as structural materials in conditions …

In-situ TEM investigation on the evolution of He bubbles and dislocation loops in Ni-based alloy irradiated by H2+ & He+ dual-beam ions

Z Zhu, W Ji, H Huang - Journal of Materials Science & Technology, 2023 - Elsevier
The synergistic evolution mechanisms of He bubbles and dislocation loops under 30 keV H
2+ & H e+ dual-beam ions irradiation at 650° C in the Ni-based alloy GH3535, which is the …

Enhanced strength of Cu-Ni-Si alloy via heterogeneous nucleation at grain boundaries during homogenization

SZ Han, IS Jeong, B Ryu, SJ Lee, JH Ahn… - Materials …, 2024 - Elsevier
Copper alloys are utilized either as cast or wrought alloys. Typically, cast alloys contain a
higher quantity of elements to enhance strength. The increased content of additive elements …

Structure of surface oxides on martensitic steel under simultaneous ion irradiation and molten LBE corrosion

C Yao, H Zhang, H Chang, T Shen, Y Zhu, L Pang… - Corrosion …, 2022 - Elsevier
Irradiation damage on corrosion process of steels in Pb or LBE melts is a main challenge for
the R&D of LFR. In this paper, A martensitic steel (SIMP) was in-situ irradiated with 247 MeV …

Research progress on LBE corrosion-resistant coatings: A review

W Zhang, J Deng, Y Zhong, M Zhou, X Qiu… - Progress in Nuclear …, 2024 - Elsevier
This paper reviews the research progress of LBE corrosion-resistant coatings based on the
conducted experiments in the published literature. Metallic coatings have been widely …

High-energy surface processing of zirconium alloys for fuel claddings of water-cooled nuclear reactors

M Slobodyan - Nuclear Engineering and Design, 2021 - Elsevier
Since 1940 s, zirconium alloys have been one of the main structural materials for
manufacturing nuclear fuel claddings of water-cooled reactors. Their functional properties …