[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 …
Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200℃
D Wang, R Zhong, Y Zhang, P Chen, Y Lan, J Yu… - Corrosion …, 2022 - Elsevier
The isothermal steam oxidation behavior of chromium-coated zirconium alloy cladding at
1200℃ is studied. The cladding substrate is Zr-1 Nb alloy with outer diameter of 9.5 mm and …
1200℃ is studied. The cladding substrate is Zr-1 Nb alloy with outer diameter of 9.5 mm and …
[HTML][HTML] Improved and Innovative Accident-Tolerant Nuclear Fuel Materials Considered for Retrofitting Light Water Reactors—A Review
RB Rebak - Corrosion and Materials Degradation, 2023 - mdpi.com
Since 2011, there has been an international effort to evaluate the behavior of newer fuel rod
materials for the retrofitting of existing light water reactors (LWR). These materials include …
materials for the retrofitting of existing light water reactors (LWR). These materials include …
[HTML][HTML] Distinctive Oxide Films Develop on the Surface of FeCrAl as the environment changes for nuclear fuel cladding
The corrosion-resistant properties of IronChromium–Aluminum (FeCrAl) alloys have been
known for nearly a century. Since the 1950s, they have been explored for application in the …
known for nearly a century. Since the 1950s, they have been explored for application in the …
[HTML][HTML] Effect of aging and α'segregation on oxidation and electrochemical behavior of FeCrAl alloys
R Rajendran, AS Chikhalikar, I Roy… - Journal of Nuclear …, 2024 - Elsevier
FeCrAl alloys are promising candidates for next generation nuclear fuel cladding
applications due to their high resistance to hydrothermal corrosion, high temperature steam …
applications due to their high resistance to hydrothermal corrosion, high temperature steam …
[HTML][HTML] Mechanistic study of incipient corrosion for nuclear grade lean-Cr FeCrAl alloys in a simulated PWR environment
Z Qu, C Meng, J Huang, Y Mei, Y Zhang, J Ma, W Liu… - Materials & Design, 2023 - Elsevier
This study systematically investigated the incipient corrosion behavior of Fe-13Cr-4.5 Al
(wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months …
(wt%) and lean-Cr (7–10 wt%) with 5Al (wt%) FeCrAl alloy with a timescale of 4 months …
Realistic performance assessment of FeCrAl-UN/U3Si2 accident tolerant fuel under loss-of-coolant accident scenario
Q Xiong, L Qian, G Song, J Yang, Y Liu, J Deng… - Reliability Engineering & …, 2024 - Elsevier
The rigorous safety requirements in the nuclear industry have necessitated the development
of accident tolerant fuels, with FeCrAl-UN/U 3 Si 2 being one of the latest innovations in this …
of accident tolerant fuels, with FeCrAl-UN/U 3 Si 2 being one of the latest innovations in this …
[HTML][HTML] Microstructure and texture evolutions in FeCrAl cladding tube during pilger processing
X Qin, R Zhang, P Du, J Pei, Q Pan, Y Cao… - Journal of Materials …, 2023 - Elsevier
The microstructure of FeCrAl cladding tubes depends on the fabricating process history. In
this study, the microstructural characteristics of wrought FeCrAl alloys during industrial pilger …
this study, the microstructural characteristics of wrought FeCrAl alloys during industrial pilger …
Processing heterogeneously structured oxide-dispersion-strengthened Fe-10Cr-6.1 Al-0.3 Zr-0.1 Y alloy for simultaneously enhanced strength and ductility
T Cao, Y Wu, P Huang, J Wang, Z Yang, F Jiang… - Journal of Materials …, 2025 - Elsevier
An oxide-dispersion-strengthened (ODS) Fe-10Cr-6.1 Al-0.3 Zr-0.1 Y alloy with a bimodal
grain size distribution was developed via a simple process of internal oxidation and powder …
grain size distribution was developed via a simple process of internal oxidation and powder …
[HTML][HTML] Effect of the redox potential on the general corrosion behavior of industrial nuclear alloys
During the last decade, the international nuclear materials community has been
investigating a robust fuel version for Light Water Reactors called Accident Tolerant Fuel …
investigating a robust fuel version for Light Water Reactors called Accident Tolerant Fuel …