Tenghong Lin , Zhaolin Shi , Hui Wang , Donghai Du
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Effects of chromium concentration on the uniform corrosion behavior of FeCrAl alloy in hydrogenated water
FeCrAl alloys are promising accident-tolerant fuel cladding candidates for light water reactors, where balancing irradiation and corrosion resistance is crucial. While lower Cr content generally enhances irradiation hardening resistance, its impact on high-temperature water corrosion remains unclear. Here, we systematically evaluated how Cr concentration (7–13 wt%) affects the uniform corrosion behavior of FeCrAl in simulated PWR environments. The experimental results showed that the metal loss due to corrosion reduces linearly with an increase in Cr concentration. Although 13 wt% Cr yields superior corrosion resistance, reducing Cr content to 7 wt% retains adequate corrosion resistance and demonstrates remarkable long-term stability, as evidenced by oxidation kinetics and nanoscale oxide characterization. These findings reveal that Cr reduction, potentially beneficial for irradiation resistance, does not significantly compromise corrosion performance, enabling cost-effective yet durable cladding designs.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.