Dislocation loops growth and radiation growth in neutron irradiated Zr-Nb alloys: rate theory modelling

被引:5
作者
Wu, L. [1 ]
Kharchenko, D. O. [2 ]
Kharchenko, V. O. [2 ]
Lysenko, O. B. [2 ]
Kupriienko, V [2 ]
Kokhan, S. [2 ]
Shuda, I. A. [3 ]
Pan, R. [1 ]
机构
[1] Nucl Power Inst China, Inst 1, 328,1st Sect,Changshundadao Rd, Chengdu 610213, Peoples R China
[2] Natl Acad Sci Ukraine, Inst Appl Phys, 58 Petropavlivska St, UA-40000 Sumy, Ukraine
[3] Sumy State Univ, 2 Rymskogo Korsakova St, UA-40007 Sumy, Ukraine
关键词
irradiation; zirconium alloys; point defects; dislocation loops; growth strain; ZIRCONIUM ALLOYS; POINT-DEFECTS; MICROSTRUCTURE EVOLUTION; DIFFUSION ANISOTROPY; INDUCED CREEP; DAMAGE; PRECIPITATION; DEPENDENCE; MECHANISMS; METALS;
D O I
10.5488/CMP.23.13604
中图分类号
O469 [凝聚态物理学];
学科分类号
070205 ;
摘要
A generalized model to study dislocation loops growth in irradiated binary Zr-based alloys is presented. It takes into account temperature effects, efficiencies of loops to absorb point defects dependent on the loop size, an influence of locality of grain boundary sink strength, and concentration of the alloying element. This model is used to describe the dynamics of loop radii growth in zirconium-niobium alloys under neutron irradiation at reactor conditions. A growth of both loop radii and strains is studied at different grain sizes, location from grain boundaries, and concentration of niobium. It is shown that locality of grain boundary sinks results in a non-uniform deformation of the crystal inside the grains. Additionally, an introduction of niobium as an alloying element decreases the loop radii but promotes the growth of local strains inside the grains.
引用
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页数:18
相关论文
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