Research progress on preparation technology of oxide dispersion strengthened steel for nuclear energy

J Wang, S Liu, B Xu, J Zhang, M Sun… - International Journal of …, 2021 - iopscience.iop.org
Nuclear energy is a low-carbon, safe, efficient, and sustainable clean energy. The new
generation of nuclear energy systems operate in harsher environments under higher …

[HTML][HTML] The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review

N Luptáková, J Svoboda, D Bártková, A Weiser… - Materials, 2024 - mdpi.com
High-performance structural materials (HPSMs) are needed for the successful and safe
design of fission and fusion reactors. Their operation is associated with unprecedented …

[HTML][HTML] Microstructure and tensile properties of Y2O3-dispersion strengthened CoCrFeNi high entropy alloys prepared via mechanical alloying using pre-alloyed …

M Zhao, J Xu, W Ye, Y Gui, J Zhao, Y Qiao… - Journal of Materials …, 2024 - Elsevier
Abstract Nano-Y 2 O 3-dispersion strengthened CoCrFeNi high entropy alloys are fabricated
via mechanical alloying and spark plasma sintering using high purity elemental powders or …

Bubble formation in helium-implanted nanostructured ferritic alloys at elevated temperatures

YR Lin, WY Chen, L Tan, DT Hoelzer, Z Yan, CY Hsieh… - Acta Materialia, 2021 - Elsevier
Helium bubble formation was examined by scanning/transmission electron microscopy
(S/TEM) in Fe-9/10Cr binary alloys and two dispersion strengthened nanostructured alloys …

Preparation and property optimization of FeCrAl-based ODS alloy by machine learning combined with wedge-shaped hot-rolling

L Deng, C Wang, J Luo, J Tu, N Guo, H Xu, P He… - Materials …, 2022 - Elsevier
In this study, oxide dispersion strengthened (ODS) steel with a composition of Fe-12% Cr-
4.5% Al-2.0% W-0.3% Y 2 O 3 (wt%) was designed by machine learning (ML) and prepared …

Deterioration of irradiation resistance of ODS-F/M steel under high concentration of helium

Z Xie, L Guo, Y Chen, Y Long, P Lv, F Li, H Luo… - Journal of Nuclear …, 2023 - Elsevier
Abstract Simultaneous Fe+ He ion irradiations of China Low Activation Martensitic (CLAM)
steel and oxide-dispersion-strengthened ferritic/martensitic (ODS-F/M) steel were carried out …

Experimental and modeling study on irradiation effect of A508-Ⅲ steel

P Lin, J Nie, W Cui, L He, S Cui, L Xiang, Y Lu… - International Journal of …, 2024 - Elsevier
Irradiation can induce microscopic defects in reactor pressure vessel (RPV) steel, resulting
in macroscopic hardening and embrittlement. This paper proposes a micro‑meso …

Chemical and structural evolution of nano-oxides from mechanical alloying to consolidated ferritic oxide dispersion strengthened steel

G Spartacus, J Malaplate, F De Geuser, I Mouton… - Acta Materialia, 2022 - Elsevier
Abstract Ferritic Oxides Dispersion Strengthened (ODS) steels are of great interest for
nuclear fission and fusion power plants. The nano-oxides embedded into the matrix provide …

Achieving strength-ductility synergy of ODS-FeCrAl alloys via heterostructured strategy

D Sun, Z Lu, X Li, S Gao, H Li - Materials Science and Engineering: A, 2025 - Elsevier
Oxide dispersion strengthened (ODS)-FeCrAl alloys are candidate structural materials for
advanced nuclear reactor applications, which have excellent strength and radiation …

Segmentation of experimental datasets via convolutional neural networks trained on phase field simulations

J Yeom, T Stan, S Hong, PW Voorhees - Acta Materialia, 2021 - Elsevier
The ability to quickly analyze large imaging datasets is vital to the widespread adoption of
modern materials characterization tools, and thus the development of new materials. Image …