Environmental degradation of structural materials in liquid lead-and lead-bismuth eutectic-cooled reactors
Liquid lead (Pb)-and lead–bismuth eutectic (LBE)-cooled fast neutron reactors (Gen-IV
LFRs) are one of the most technologically mature fission reactor technologies, due to their …
LFRs) are one of the most technologically mature fission reactor technologies, due to their …
Current status of materials development of nuclear fuel cladding tubes for light water reactors
Z Duan, H Yang, Y Satoh, K Murakami, S Kano… - … Engineering and Design, 2017 - Elsevier
Abstract Zirconium-based (Zr-based) alloys have been widely used as materials for the key
components in light water reactors (LWRs), such as fuel claddings which suffer from …
components in light water reactors (LWRs), such as fuel claddings which suffer from …
[HTML][HTML] Exploring the phase stability, mechanical and thermodynamic properties of FeCrAl ternary alloy
Y Pan - Journal of Materials Research and Technology, 2023 - Elsevier
Although FeCrAl ternary alloy is a promising high-temperature material, the structural
features of the FeCrAl remains controversial. To understand the structural features and the …
features of the FeCrAl remains controversial. To understand the structural features and the …
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
Abstract Development of nuclear grade, iron-based wrought FeCrAl alloys has been initiated
for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys …
for light water reactor (LWR) fuel cladding to serve as a substitute for zirconium-based alloys …
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
Abstract The Fe–Cr–Al alloy system has the potential to form an important class of enhanced
accident-tolerant cladding materials in the nuclear power industry owing to the alloy …
accident-tolerant cladding materials in the nuclear power industry owing to the alloy …
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
FeCrAl alloys are currently under consideration for accident-tolerant fuel cladding
applications in light water reactors owing to their superior high-temperature oxidation and …
applications in light water reactors owing to their superior high-temperature oxidation and …
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
Abstract Model FeCrAl alloys with varying compositions (Fe (10–18) Cr (10–6) Al at.%) have
been neutron irradiated at~ 320 to damage levels of~ 7 displacements per atom (dpa) to …
been neutron irradiated at~ 320 to damage levels of~ 7 displacements per atom (dpa) to …
Laser-clad FeCrAl/TiC composite coating on ferrite/martensitic steel: Significant grain refinement and wear resistance enhancement induced by adding TiC
By employing laser cladding, the surface of a ferritic/martensite (F/M) steel was coated with
FeCrAl metallic and FeCrAl/TiC composite coatings with their microstructures and wear …
FeCrAl metallic and FeCrAl/TiC composite coatings with their microstructures and wear …
[HTML][HTML] A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding
At present, the Department of Energy (DOE) in Unite State are directing the efforts of
developing accident tolerant fuel (ATF) technology. As the first barrier of nuclear fuel system …
developing accident tolerant fuel (ATF) technology. As the first barrier of nuclear fuel system …
Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in Japan
S Ukai, K Sakamoto, S Ohtsuka, S Yamashita… - Journal of Nuclear …, 2023 - Elsevier
Following the severe accident at the Fukushima Daiichi nuclear power plant in 2011,
recrystallized FeCrAl-ODS claddings have been developed in Japan as an accident-tolerant …
recrystallized FeCrAl-ODS claddings have been developed in Japan as an accident-tolerant …