Positron annihilation investigation of hardening behavior induced by Fe2+ irradiation in low-Cr FeCrAl alloys
M Niu, H Wang, X Huang - Journal of Materials Research and Technology, 2023 - Elsevier
Abstract Compared with 13Cr–FeCrAl alloy, micro-alloyed low-Cr FeCrAl alloy is expected
to provide higher potential for application as accident-tolerant fuel (ATF) cladding material …
to provide higher potential for application as accident-tolerant fuel (ATF) cladding material …
[HTML][HTML] In-situ TEM investigation of defect evolution in FeCrAl during post-irradiation annealing
Y Luo, C Zhan, Y Zhong, Y Zou, R Zhang… - Journal of Materials …, 2023 - Elsevier
Aiming to newly-developed FeCrAl alloys for accident-tolerant fuels (ATF) in light water
reactors (LWR), an in-situ investigation of scan transmission electron microscopy (STEM) …
reactors (LWR), an in-situ investigation of scan transmission electron microscopy (STEM) …
The effect of sample thickness on micro-mesoscale tensile properties of 304SS, HT-9, and CuCrZr
Small scale mechanical testing has gained significant attention in recent times due to its
advantages for materials research and development; however, the ability to extend small …
advantages for materials research and development; however, the ability to extend small …
Post-irradiation examination of low burnup U3Si5 and UN-U3Si5 composite fuels
This work presents post-irradiation examination data on UN-U 3 Si 5 and U 3 Si 5 fuels at
low burnup (ie,< 10–15 GWd/tHM) with Kanthal AF® cladding. The results suggest good …
low burnup (ie,< 10–15 GWd/tHM) with Kanthal AF® cladding. The results suggest good …
In-situ proton irradiation-corrosion study of ATF candidate alloys in simulated PWR primary water
Irradiation enhanced corrosion behavior of Accident Tolerant Fuel candidate alloys T91 and
Fe15Cr4Al were evaluated using in-situ proton irradiation-corrosion experiments in …
Fe15Cr4Al were evaluated using in-situ proton irradiation-corrosion experiments in …
The Impact of Zirconium (Zr) on the Irradiation-Induced Hardening of Zr Doped Fecral Alloys
M ING, S Shen, X Zhang, L Hao, S Wang… - Available at SSRN … - papers.ssrn.com
Comprehensive study of irradiation behavior of zirconium-doped FeCrAl alloys with
improved mechanical properties remains elusive. In this study, FeCrAl alloys containing 0 …
improved mechanical properties remains elusive. In this study, FeCrAl alloys containing 0 …
Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
The Advanced Fuels Campaign within the Nuclear Technology Research and Development
program of the Department of Energy Office of Nuclear Energy is seeking to improve the …
program of the Department of Energy Office of Nuclear Energy is seeking to improve the …
Analysis and Experimental Qualification of an Irradiation Capsule Design for Testing Pressurized Water Reactor Fuel Cladding in the High Flux Isotope Reactor
The Advanced Fuels Campaign within the Fuel Cycle Research and Development program
of the Department of Energy Office of Nuclear Energy is currently investigating a number of …
of the Department of Energy Office of Nuclear Energy is currently investigating a number of …