Primary radiation damage in 3C-SiC under strain field studied with molecular dynamics simulation

被引:1
|
作者
Wang, Dong [1 ]
Yang, Fei [2 ]
Lv, Junnan [1 ]
Zhu, Yabin [3 ,4 ]
Yao, Lifu [1 ]
Gao, Ning [5 ,6 ]
Zhang, Zhengjun [7 ,8 ]
机构
[1] Nucl Power Inst China, Natl Key Lab Nucl Reactor Technol, Chengdu 610213, Peoples R China
[2] China Acad Engn Phys, Inst Nucl Phys & Chem, Mianyang 621900, Peoples R China
[3] Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China
[4] Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China
[5] Shandong Univ, Inst Frontier & Interdisciplinary Sci, Qingdao 266237, Peoples R China
[6] Shandong Univ, Key Lab Particle Phys & Particle Irradiat MOE, Qingdao 266237, Peoples R China
[7] Tsinghua Univ, Sch Mat Sci & Engn, Key Lab Adv Mat MOE, Beijing 100084, Peoples R China
[8] Collaborat Innovat Ctr Adv Nucl Energy Technol, Beijing 100084, Peoples R China
基金
中国国家自然科学基金;
关键词
SiC; Radiation damage; Defects; Threshold displacement energy; Stress/strain effect; THRESHOLD DISPLACEMENT ENERGIES; DEFECT PRODUCTION; COLLISION CASCADES; SILICON-CARBIDE; MD SIMULATIONS; POINT-DEFECTS; HIGH-PRESSURE; AMORPHIZATION; DEFORMATION; TEMPERATURE;
D O I
10.1016/j.jnucmat.2024.155297
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Cubic silicon carbide (3C-SiC) has been selected as candidate structural and cladding materials for advanced nuclear systems due to its excellent properties. The influence of external mechanical load, thermal stress and radiation damage induced stress/strain field on radiation behavior in 3C-SiC is not well understood. In this work, the primary radiation damages in 3C-SiC under strain field have been investigated with molecular dynamics (MD) simulation. The results demonstrate that the strain field is of significant importance on the radiation damages in 3C-SiC. The threshold displacement energy decreases with strain from compression to tension. During displacement cascade and annealing, the surviving defect, defect clustered fraction and cluster size increase at the tensile state, while the defect recombination ratio decreases. Among the generated point defects, the vacancy and interstitial contribute to the majority of defect production increase under tensile strain. The higher energy of primary knock-on atom (PKA) results in more defect production but suffers from the same strain effect. High temperature increases the defect recombination ratio but reduces the surviving defect number during both displacement cascade and annealing process. Comparing with compressive state, tensile state exhibits a more significant temperature effect on defect production and recombination in displacement cascades, while a less significant temperature effect on defect cluster. All these results indicate that the influence of stress/strain state, especially tensile state, should be seriously taken into account for the application of SiC in nuclear reactor environment.
引用
收藏
页数:12
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