Radiation damage in nanostructured materials
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 …
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
In-situ mechanical testing in a scanning electron microscope (SEM) equipped with an
electron backscatter diffraction (EBSD) system has quickly gained popularity, particularly …
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 …
to favour a BCC crystal structure, and to be suitable for high temperature environments, was …
Flash electropolishing of BCC Fe and Fe-based alloys
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 …
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
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° …
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
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 …
predicted using an integrated modeling framework. Multiple physical mechanisms such as …
Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose
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 …
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
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) …
(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
This work systematically reports grain boundary radiation-induced segregation (RIS), and
insights into RIS mechanisms, in FeCrAl alloys. Recently, FeCrAl alloys have received …
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
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 …
nano-oxides (NOs)(size of∼ 2–3 nm) are one of the best candidates for structural …