Unveiling deformation behavior and damage mechanism of irradiated high entropy alloys

Shuo Wang ¹Yang Chen ¹Jia Li ¹Bin Liu ²Ruiqian Zhang ³Peter K Liaw ⁴Qihong Fang¹

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作者信息

1. State Key Laboratory of Advanced Design and Manufacturing for Vehicle Body,College of Mechanical and Vehicle Engineering,Hunan University,Changsha 410082,China
2. State Key Laboratory of Powder Metallurgy,Central South University,Changsha 410083,China
3. Science and Technology on Reactor Fuel and Materials Laboratory,Nuclear Power Institute of China,Chengdu 610213,China
4. Department of Materials Science and Engineering,The University of Tennessee,Knoxville,TN 37996,USA
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Abstract

The oxide dispersion strengthening(ODS)high entropy alloy(HEA)exhibits the high elevated temper-ature performance and radiation resistance due to severe atomic lattice distortion and oxide particles dispersed in matrix,which is expected to become the most promising structural material in the next generation of nuclear energy systems.However,microstructure and damage evolution of irradiated ODS HEA under loading remain elusive at submicron scale using the existing simulations owing to a lack of atomic-lattice-distortion information from a micromechanics description.Here,the random field theory informed discrete dislocation dynamics simulations based on the results of high-resolution transmission electron microscopy are developed to study the dislocation behavior and damage evolution in ODS HEA considering the influence of severe lattice distortion and nanoscale oxide particle.Noteworthy,the dam-age behavior shows an unusual trend of the decreasing-to-increasing transition with the continuous load-ing process.There are two main types of damage micromechanics generated in irradiated ODS HEA:the dislocation loop damage in which the damage is controlled by irradiation-induced dislocation loops and their evolution,the strain localization damage in which the damage comes from the dislocation multipli-cation in the local plastic region.The oxide particle hinders the dislocation movement in the main slip plane,and the lattice distortion induces the dislocation sliding to the secondary slip plane,which pro-motes the dislocation cross-slip and dislocation loop annihilation,and thus reduces the material damage in the elastic damage stage.These findings can deeply understand atomic-scale damage mechanism and guide the design of ODS HEA with high radiation resistance.

Key words

Oxide dispersion strengthening/High entropy alloy/Radiation/Dislocation/Damage model

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基金项目

National Natural Science Foundation of China(U2267252)

National Natural Science Foundation of China(12372069)

National Natural Science Foundation of China(12302083)

National Natural Science Foundation of China(12172123)

China Postdoctoral science Foundation(2023M731061)

Natural Science Foundation of Hunan Province(2022JJ20001)

Hunan Provincial Innovation Foundation for Postgraduate(CX20220378)

National Science Foundation(DMR-1611180)

National Science Foundation(1809640)

National Science Foundation(2226508)

出版年

2024

材料科学技术(英文版)

中国金属学会中国材料研究学会中国科学院金属研究所

材料科学技术(英文版)

CSTPCDCSCD

影响因子：0.657

ISSN：1005-0302

参考文献量96

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