Superior radiation tolerance via reversible disordering–ordering transition of coherent superlattices

J Du, S Jiang, P Cao, C Xu, Y Wu, H Chen, E Fu… - Nature materials, 2023 - nature.com
Materials capable of sustaining high radiation doses at a high temperature are required for
next-generation fission and future fusion energy. To date, however, even the most promising …

Using lifetime of point defects for dislocation bias in bcc Fe

J Hao, L Casillas-Trujillo, H Xu - Current Opinion in Solid State and …, 2022 - Elsevier
The interaction between dislocations and point defects is key to deformation processes and
microstructural evolution of structural materials. In this work, we compute the lifetime of point …

Enhanced irradiation tolerance of a medium entropy alloy via precipitation and dissolution of nanoprecipitates

J Han, Y Zhang, Z Sun, Y Zhang, Y Zhao, L Sun… - Journal of Nuclear …, 2023 - Elsevier
High/medium entropy alloys (HEAs/MEAs) are good candidates for nuclear applications due
to the excellent mechanical properties, good corrosion resistance and radiation resistance …

Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels

E Getto, K Sun, AM Monterrosa, Z Jiao… - Journal of Nuclear …, 2016 - Elsevier
The void swelling and microstructure evolution of ferritic-martensitic alloys HT9, T91 and T92
were characterized following irradiation with Fe++ ions at 460° C to damage levels of 75 …

Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa

MB Toloczko, FA Garner, VN Voyevodin… - Journal of Nuclear …, 2014 - Elsevier
In order to study the potential swelling behavior of the ODS ferritic alloy MA957 at very high
dpa levels, specimens were prepared from pressurized tubes that were unirradiated …

The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 C

JG Gigax, E Aydogan, T Chen, D Chen, L Shao… - Journal of Nuclear …, 2015 - Elsevier
Ion beam scanning or “rastering” is a technique that is frequently used to uniformly cover a
larger specimen area during ion irradiation. In this study, we addressed the effects of …

Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

T Chen, E Aydogan, JG Gigax, D Chen, J Wang… - Journal of Nuclear …, 2015 - Elsevier
A dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy, with improved corrosion and
oxidation resistance exhibits promising void swelling resistance and microstructural stability …

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9

E Getto, Z Jiao, AM Monterrosa, K Sun… - Journal of Nuclear …, 2015 - Elsevier
Void evolution in Fe++-irradiated ferritic-martensitic alloy HT9 was characterized in the
temperature range of 400–480° C between doses of 25 and 375 displacements per atom …

A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals

Y Li, A French, Z Hu, A Gabriel, LR Hawkins… - Journal of Nuclear …, 2023 - Elsevier
We propose and demonstrate a microstructurally-based experimental method to quantitively
determine the depth regions in self-ion-irradiated metals that are affected by the injected …

Temperature dependent dispersoid stability in ion-irradiated ferritic-martensitic dual-phase oxide-dispersion-strengthened alloy: Coherent interfaces vs. incoherent …

T Chen, JG Gigax, L Price, D Chen, S Ukai, E Aydogan… - Acta Materialia, 2016 - Elsevier
In this study, the microstructure of a 12Cr ferritic-martensitic oxide-dispersion-strengthened
(ODS) alloy is studied before and after Fe ion irradiation up to 200 peak displacements per …