Atomistic insights into interactions between oxygen and α–Zr (101-1) surface

The oxidation corrosion is a crucial challenge for zirconium (Zr) alloys as cladding materials in fission power reactors. In the present study, a first-principles approach is employed for understanding behaviors of oxygen adsorbed on the Zr (101-1) surface. It is found that the Zr substrate is react...

Full description

Bibliographic Details
Main Authors: Zhixiao Liu, Wangyu Hu, Hiuqiu Deng
Format: Article
Language:English
Published: Elsevier 2021-06-01
Series:Nuclear Materials and Energy
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S2352179121000582
Description
Summary:The oxidation corrosion is a crucial challenge for zirconium (Zr) alloys as cladding materials in fission power reactors. In the present study, a first-principles approach is employed for understanding behaviors of oxygen adsorbed on the Zr (101-1) surface. It is found that the Zr substrate is reactive to O species. Electrons in the 4d band of the metallic substrate tend to migrate to antibonding orbitals of the adsorbed O2 molecule, leading to breaking the O-O bond and releasing energy. Several diffusion paths for an adsorbed O atom migrating to the subsurface interstitial site are proposed. It is found that the lowest diffusion barrier is only 0.08 eV. Therefore, it can be inferred that the Zr (101-1) surface suffers fast oxidation kinetics.
ISSN:2352-1791