Peculiarities of interaction between oxygen and solute/vacancy in commercial-type zirconium-based alloys: A first-principles study

被引:0
|
作者
Pan, Rongjian [1 ]
Kharchenko, Vasyl O. [2 ,3 ]
Kharchenko, Dmitrii O. [2 ]
Xin, Tianyuan [1 ]
Qin, Jiantao [1 ]
Wu, Lu [1 ]
机构
[1] First Sub Inst, Nucl Power Inst China, Chengdu 610005, Peoples R China
[2] Natl Acad Sci Ukraine, Inst Appl Phys, 58 Petropavlovskaya St, UA-40000 Sumy, Ukraine
[3] Sumy State Univ, 2 Rimskii Korsakov St, UA-40007 Sumy, Ukraine
来源
MATERIALS TODAY COMMUNICATIONS | 2024年 / 38卷
基金
中国国家自然科学基金;
关键词
Ab-initio calculations; Zirconium alloys; Corrosion rate; Solute-oxygen binding; CLADDING CORROSION BEHAVIOR; SOLUTE-VACANCY BINDING; ZR-NB ALLOYS; AUTOCLAVE CORROSION; OXIDE LAYERS; MECHANISMS; ZIRCALOY-4; AIR; IRRADIATION; OXIDATION;
D O I
10.1016/j.mtcomm.2023.107942
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Unveiling the interaction between dissolved oxygen and solutes/vacancies during the initial stages of oxide layer formation at microscale is significant for the peculiarities of Zr-based alloys oxidation exposed in PWRs or LWRs. We perform ab-initio calculations of the diluted zirconium-based alloys with dissolved Nb and Sn solutes, vacancy and oxygen atom and discuss the solute-oxygen and vacancy-oxygen binding. Our analysis shows that with increasing content of Nb solutes the attractive interaction between niobium and oxygen becomes much stronger, which results in a decrease in corrosion rate of these alloys at the bre-breakaway regime caused by diffusion of oxygen. An increase in content of Sn in an alloy results in enforce of the repulsive interaction between Sn atom and oxygen, which causing tin-enriched alloys are characterized by an increased corrosion rate. We conclude that the dissolved oxygen can be localized near Nb atom rather than near Sn atom if both impurities are secondnearest neighbors, the dissolved oxygen can capture single vacancy and small vacancy clusters in zirconium matrix. This study provides a deep insight into the details of oxygen segregation in zirconium-based alloys exploited in nuclear-power plants.
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页数:9
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