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 …

Towards a reliable nanohardness-dose correlation of ion-irradiated materials from nanoindentation tests: A case study in proton-irradiated vanadium

S Chen, J Yuan, S Wang, L Mei, J Yan, L Li… - International Journal of …, 2023 - Elsevier
Nanoindentation has been commonly used for evaluating the hardening effects of ion-
irradiated materials. Nonetheless, establishing a reliable correlation between the hardness …

Development and additive manufacturing of oxide dispersion strengthened inconel 718: Thermochemical and experimental studies

MY Yalcin, B Derin, E Aydogan - Journal of Alloys and Compounds, 2022 - Elsevier
In this study, a new grade of Inconel 718 alloy (IN718) strengthened by nano-oxides has
been designed and produced. The alloy composition of 0.3 wt% Y 2 O 3–IN718 has been …

Intergranular corrosion behavior of low-chromium ferritic stainless steel without Cr-carbide precipitation after aging

S Hu, Y Mao, X Liu, EH Han, H Hänninen - Corrosion Science, 2020 - Elsevier
The intergranular corrosion behavior of the low-chromium ferritic stainless steel without Cr-
carbide precipitation was investigated by the methods of qualitative and quantitative …

[HTML][HTML] Insights into hardening, plastically deformed zone and geometrically necessary dislocations of two ion-irradiated FeCrAl (Zr)-ODS ferritic steels: A combined …

P Song, K Yabuuchi, P Spaetig - Acta Materialia, 2022 - Elsevier
As one of promising candidate materials for fuel claddings and structural components in the
Gen-IV fission reactors, FeCrAl (Zr)-ODS ferritic steels were studied to well understand the …

Effect of zirconium content on mechanical properties of ODS FeCrAl alloy

H Jia, R Zhang, D Long, Y Sun, Z Zhou - Materials Science and …, 2022 - Elsevier
The aim of this work is to investigate the effect of zirconium content on the mechanical
properties of ODS FeCrAl alloys, a kind of promising cladding materials for advance nuclear …

In-situ radiation response of additively manufactured modified Inconel 718 alloys

E Aydogan, O El-Atwani, B Erdem, WY Chen, M Li… - Additive …, 2022 - Elsevier
In this study, a novel alloy of modified Inconel 718 produced by laser powder bed fusion is
studied before and after in-situ Kr irradiation up to 3 dpa at 200 and 450° C. Before …

Helium irradiation induced ultra-high strength nanotwinned Cu with nanovoids

C Fan, Q Li, J Ding, Y Liang, Z Shang, J Li, R Su, J Cho… - Acta Materialia, 2019 - Elsevier
There are increasing studies that show nanotwinned (NT) metals have enhanced radiation
tolerance. However, the mechanical deformability of irradiated nanotwinned metals is a …

Atomic-scale evidence for the intergranular corrosion mechanism induced by co-segregation of low-chromium ferritic stainless steel

S Hu, EH Han, X Liu - Corrosion Science, 2021 - Elsevier
The composition distribution around grain boundaries of low-chromium ferritic stainless
steels was investigated by the techniques of three-dimensional atom probe and focused ion …

Microstructure evolution and void swelling of ODS ferritic/martensitic steel under high damage irradiation

F Li, L Guo, Y Chen, Y Long, Y Wei, Z Xie, H Luo… - Materials …, 2023 - Elsevier
The ODS ferritic/martensitic (ODS-FM) steel was irradiated up to 500 dpa at 550° C with 2.5
MeV Fe 2+ ions to investigate the microstructure evolution under low to very high doses …