Research progress on zirconium alloys: applications, development trend, and degradation mechanism in nuclear environment
BO Okonkwo, Z Li, L Li, J Wang, EH Han - Corrosion Reviews, 2024 - degruyter.com
In this paper, the research progress of zirconium (Zr) alloys is critically reviewed from the
aspects of application, development status, and degradation mechanism in a nuclear …
aspects of application, development status, and degradation mechanism in a nuclear …
Corrosion of FeCrAl-1Nb alloy in Deaerated Water at 290℃ and 7MPa: The Oxidation Behavior of Grain Boundary
Y Hu, Y Ling, X Zhao, W Zhang, F Zhao, W Wang… - Corrosion …, 2024 - Elsevier
An investigation into the grain boundary corrosion behavior of a FeCrAl-1Nb alloy at 290℃
and 7 MPa deaerated solution comprising lithium hydroxide and boric acid was conducted …
and 7 MPa deaerated solution comprising lithium hydroxide and boric acid was conducted …
Nb speciation and microstructural characterization of the oxide layer formed on neutron-irradiated Zr-2.5 Nb alloy in high-temperature water
It is crucial to understand the degradation mechanisms of the alloy Zr-2.5 Nb, which make
the pressure boundary in Canada Deuterium Uranium reactors. In the present study, Zr-2.5 …
the pressure boundary in Canada Deuterium Uranium reactors. In the present study, Zr-2.5 …