中国物理B ›› 2024, Vol. 33 ›› Issue (1): 16105-16105.doi: 10.1088/1674-1056/ad08a6

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Effect of grain size on gas bubble evolution in nuclear fuel: Phase-field investigations

Dan Sun(孙丹)1, Qingfeng Yang(杨青峰)1, Jiajun Zhao(赵家珺)2, Shixin Gao(高士鑫)1, Yong Xin(辛勇)1, Yi Zhou(周毅)1, Chunyu Yin(尹春雨)1, Ping Chen(陈平)1,†, Jijun Zhao(赵纪军)2, and Yuanyuan Wang(王园园)2,‡   

  1. 1 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China;
    2 Key Laboratory of Materials Modification by Laser, Ion, and Electron Beams, Dalian University of Technology, Dalian 116024, China
  • 收稿日期:2023-08-03 修回日期:2023-09-28 接受日期:2023-11-02 出版日期:2023-12-13 发布日期:2024-01-03
  • 通讯作者: Ping Chen, Yuanyuan Wang E-mail:Chenping_npic@163.com;yuanyuanwang@dlut.edu.cn
  • 基金资助:
    Project supported by the National Natural Science Foundation of China (Grant Nos. U2167217, 12205286, and 11905025) and the National MCF Energy Research and Development Program of China (Grant No. 2018YFE0308105).

Effect of grain size on gas bubble evolution in nuclear fuel: Phase-field investigations

Dan Sun(孙丹)1, Qingfeng Yang(杨青峰)1, Jiajun Zhao(赵家珺)2, Shixin Gao(高士鑫)1, Yong Xin(辛勇)1, Yi Zhou(周毅)1, Chunyu Yin(尹春雨)1, Ping Chen(陈平)1,†, Jijun Zhao(赵纪军)2, and Yuanyuan Wang(王园园)2,‡   

  1. 1 Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China;
    2 Key Laboratory of Materials Modification by Laser, Ion, and Electron Beams, Dalian University of Technology, Dalian 116024, China
  • Received:2023-08-03 Revised:2023-09-28 Accepted:2023-11-02 Online:2023-12-13 Published:2024-01-03
  • Contact: Ping Chen, Yuanyuan Wang E-mail:Chenping_npic@163.com;yuanyuanwang@dlut.edu.cn
  • Supported by:
    Project supported by the National Natural Science Foundation of China (Grant Nos. U2167217, 12205286, and 11905025) and the National MCF Energy Research and Development Program of China (Grant No. 2018YFE0308105).

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摘要： Numerous irradiation-induced gas bubbles are created in the nuclear fuel during irradiation, leading to the change of microstructure and the degradation of mechanical and thermal properties. The grain size of fuel is one of the important factors affecting bubble evolution. In current study, we first predict the thermodynamic behaviors of point defects as well as the interplay between vacancy and gas atom in both UO2 and U3Si2 according to ab initio approach. Then, we establish the irradiation-induced bubble phase-field model to investigate the formation and evolution of intra- and inter-granular gas bubbles. The effects of fission rate and temperature on the evolutions of bubble morphologies in UO2 and U3Si2 have been revealed. Especially, a comparison of porosities under different grain sizes is examined and analyzed. To understand the thermal conductivity as functions of grain size and porosity, the heat transfer capability of U3Si2 is evaluated.

关键词: grain size, point defects, fission gas bubble

Abstract: Numerous irradiation-induced gas bubbles are created in the nuclear fuel during irradiation, leading to the change of microstructure and the degradation of mechanical and thermal properties. The grain size of fuel is one of the important factors affecting bubble evolution. In current study, we first predict the thermodynamic behaviors of point defects as well as the interplay between vacancy and gas atom in both UO2 and U3Si2 according to ab initio approach. Then, we establish the irradiation-induced bubble phase-field model to investigate the formation and evolution of intra- and inter-granular gas bubbles. The effects of fission rate and temperature on the evolutions of bubble morphologies in UO2 and U3Si2 have been revealed. Especially, a comparison of porosities under different grain sizes is examined and analyzed. To understand the thermal conductivity as functions of grain size and porosity, the heat transfer capability of U3Si2 is evaluated.

Key words: grain size, point defects, fission gas bubble

中图分类号:  (Grain and twin boundaries)

  • 61.72.Mm
61.72.J- (Point defects and defect clusters) 61.72.-y (Defects and impurities in crystals; microstructure)