Abstract To shed a light on Xe bubble nucleation in U-Mo fuel from the view of primary irradiation damage, a reported U-Mo-Xe potential under the framework of embedded atom method has been modified within the range of short and intermediate atomic distance. The modified potential can better describe the interactions between energetic particles, and can accurately reproduce the threshold displacement energy surface calculated by the first-principles method. Then, molecular dynamics simulations of primary irradiation damage in U-Mo-Xe system have been conducted under different contents. The raise of Xe concentration brings about a remarkable promotion in residual defect quantity and generates bubbles in more over-pressured state, which suggests an acceleration of irradiation damage under the accumulation of the fission gas. Meanwhile, the addition of Mo considerably reduces the residual defect count and hinders irradiation-induced Xe diffusion especially at high contents of Xe, corroborating the importance of high Mo content in mitigation of irradiation damage and swelling behavior in U-Mo fuel. In particular, the variation of irradiation damage with respect to contents suggests a necessity of taking into account the influence of local components on defect evolution in mesoscale simulations.
Fund: The authors acknowledge Yi Wang for providing inspiration for dealing with technical problems. Project supported by the National Key Research and Development Program of China (Grant No. 2017YFB0702401) and the National Natural Science Foundation of China (Grant No. 51631005).
Corresponding Authors:
Jian-Bo Liu
E-mail: jbliu@mail.tsinghua.edu.cn
Cite this article:
Wen-Hong Ouyang(欧阳文泓), Jian-Bo Liu(刘剑波), Wen-Sheng Lai(赖文生),Jia-Hao Li(李家好), and Bai-Xin Liu(柳百新) Atomic simulations of primary irradiation damage in U-Mo-Xe system 2023 Chin. Phys. B 32 036101
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