Radiation damage in nanostructured materials

X Zhang, K Hattar, Y Chen, L Shao, J Li, C Sun… - Progress in Materials …, 2018 - Elsevier
Materials subjected to high dose irradiation by energetic particles often experience severe
damage in the form of drastic increase of defect density, and significant degradation of their …

[HTML][HTML] Recent progress in analysis of strain-induced phenomena in irradiated metallic materials and advanced alloys using SEM-EBSD in-situ tensile testing

MN Gussev, DA McClintock, TS Byun… - Current Opinion in Solid …, 2024 - Elsevier
In-situ mechanical testing in a scanning electron microscope (SEM) equipped with an
electron backscatter diffraction (EBSD) system has quickly gained popularity, particularly …

Radiation damage tolerance of a novel metastable refractory high entropy alloy V2. 5Cr1. 2WMoCo0. 04

D Patel, MD Richardson, B Jim, S Akhmadaliev… - Journal of nuclear …, 2020 - Elsevier
A novel multicomponent alloy, V 2.5 Cr 1.2 WMoCo 0.04, produced from elements expected
to favour a BCC crystal structure, and to be suitable for high temperature environments, was …

Flash electropolishing of BCC Fe and Fe-based alloys

Y Li, M Song, P Zhu, YR Lin, Z Qi, Y Zhao… - Journal of Nuclear …, 2023 - Elsevier
The preparation of transmission electron microscopy (TEM) samples is a critical step in the
characterization of materials, and the focused ion beam (FIB) technique is a commonly used …

Emulation of fast reactor irradiated T91 using dual ion beam irradiation

S Taller, Z Jiao, K Field, GS Was - Journal of Nuclear Materials, 2019 - Elsevier
Dual ion irradiations using 5 MeV defocused Fe 2+ ions and co-injected He 2+ ions were
conducted on a ferritic-martensitic steel alloy, T91, in the temperature range of 406° C–570° …

Mechanism-based modeling of thermal and irradiation creep behavior: An application to ferritic/martensitic HT9 steel

W Wen, A Kohnert, MA Kumar, L Capolungo… - International Journal of …, 2020 - Elsevier
In this work, the creep behavior of HT9 steel in both thermal and irradiation environments is
predicted using an integrated modeling framework. Multiple physical mechanisms such as …

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose

C Zheng, ER Reese, KG Field, E Marquis… - Journal of Nuclear …, 2019 - Elsevier
A ferritic/martensitic steel, HT9, was irradiated in the BOR-60 reactor to∼ 17.1 and∼ 35.1
displacements per atom (dpa) at 650±23 K (377±23° C). Irradiated samples were …

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature

C Zheng, ER Reese, KG Field, T Liu, EA Marquis… - Journal of Nuclear …, 2020 - Elsevier
The ferritic/martensitic steel HT9 was irradiated in the BOR-60 reactor at 650, 690 and 730 K
(377, 417 and 457° C) to doses between∼ 14.6–18.6 displacements per atom (dpa) …

Systematic study of radiation-induced segregation in neutron-irradiated FeCrAl alloys

PV Patki, TJ Pownell, Y Bazarbayev, D Zhang… - Journal of Nuclear …, 2023 - Elsevier
This work systematically reports grain boundary radiation-induced segregation (RIS), and
insights into RIS mechanisms, in FeCrAl alloys. Recently, FeCrAl alloys have received …

Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties

E Aydogan, JS Weaver, U Carvajal-Nunez… - Acta Materialia, 2019 - Elsevier
Nanostructured ferritic alloys (NFAs) having sub-micron grain size with a high density of
nano-oxides (NOs)(size of∼ 2–3 nm) are one of the best candidates for structural …