Microstructural evolution of gas bubbles and thermal conductivity in UO2-BeO bicrystal

被引:0
|
作者
Chuanxin Liang
Yunting Su
Mengyuan Hao
Tianjiao Dong
Hengfeng Gong
Wenbo Liu
Dong Wang
机构
[1] Xi’an Jiaotong University,Center of Microstructure Science, Frontier Institute of Science and Technology, State Key Laboratory for Mechanical Behavior of Materials
[2] China Nuclear Power Technology Research Institute Co.,Nuclear Fuel and Materials Department
[3] Ltd,Department of Nuclear Science and Technology
[4] Xi’an Jiaotong University,undefined
来源
Journal of Materials Science | 2023年 / 58卷
关键词
D O I
暂无
中图分类号
学科分类号
摘要
UO2-BeO is an important composite nuclear fuel with high thermal conductivity. The impact of grain boundaries between UO2-UO2 and phase boundaries between UO2-BeO on the bubble evolution and the thermal conductivity in nuclear fuels is significant. In this study, we utilize a 3D phase field model to examine the influence of these boundaries on the nucleation and growth of bubbles in a bicrystalline UO2-BeO. Our simulations reveal that the diffusion of vacancies and gas atoms towards the phase boundaries results in bubbles preferentially forming at the phase boundaries. Intergranular bubbles possess an asymmetrical lectical shape due to the long-range diffusion-controlled boundary migration and the different defect production rate on the both sides. Spherical intragranular bubbles appear after the intergranular bubbles with high defects production rates and large grain size. The effective thermal conductivity decreases with the irradiation time and shows three distinct stages for systems that have both inter- and intragranular bubbles.
引用
收藏
页码:11944 / 11956
页数:12
相关论文
共 50 条
  • [1] Microstructural evolution of gas bubbles and thermal conductivity in UO2-BeO bicrystal
    Liang, Chuanxin
    Su, Yunting
    Hao, Mengyuan
    Dong, Tianjiao
    Gong, Hengfeng
    Liu, Wenbo
    Wang, Dong
    JOURNAL OF MATERIALS SCIENCE, 2023, 58 (29) : 11944 - 11956
  • [2] Thermal conductivity of UO2-BeO pellet
    Ishimoto, S
    Hirai, M
    Ito, K
    Korei, Y
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1996, 33 (02) : 134 - 140
  • [3] Microstructure-Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO
    Zhou, Wenzhong
    Revankar, Shripad T.
    Liu, Rong
    Beni, Mehrdad Shahmohammadi
    HEAT TRANSFER ENGINEERING, 2018, 39 (09) : 760 - 774
  • [4] FULLY COUPLED MULTIPHYSICS SIMULATION OF ENHANCED THERMAL CONDUCTIVITY UO2-BEO FUEL BEHAVIOR
    Liu, Rong
    Zhou, Wenzhong
    PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2015, VOL 6B, 2016,
  • [5] ENHANCED THERMAL CONDUCTIVITY UO2-BEO FUELS FABRICATION METHODS AND THEIR THERMAL PERFORMANCE IN LIGHT WATER REACTORS
    Zhou, Wenzhong
    Liu, Rong
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,
  • [6] Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2-BeO fuel in light water reactors
    Zhou, Wenzhong
    Liu, Rong
    Revankar, Shripad T.
    ANNALS OF NUCLEAR ENERGY, 2015, 81 : 240 - 248
  • [7] Fabrication of UO2-BeO composite pellets with superior thermal conductivity based on multi-parameter theoretical analyses
    Gao, Rui
    Yang, Zhenliang
    Li, Bingqing
    Yan, Biaojie
    Cheng, Liang
    Wang, Yun
    Zhong, Yi
    Huang, Qiqi
    Wang, Zhiyi
    Chu, Mingfu
    Bai, Bin
    Zhu, Xueyan
    Zhang, Pengcheng
    Li, Rui
    Liu, Tong
    JOURNAL OF NUCLEAR MATERIALS, 2020, 542
  • [8] Fully coupled multiphysics modeling of enhanced thermal conductivity UO2-BeO fuel performance in a light water reactor
    Liu, R.
    Zhou, W.
    Shen, P.
    Prudil, A.
    Chan, P. K.
    NUCLEAR ENGINEERING AND DESIGN, 2015, 295 : 511 - 523
  • [9] Neutronic study of UO2-BeO fuel with various claddings
    Chen, Shengli
    Yuan, Cenxi
    NUCLEAR MATERIALS AND ENERGY, 2020, 22
  • [10] Analysis of UO2-BeO fuel performance using FRAPCON
    20160902018977
    (1) Purdue University, West Lafayette; IN, United States, 1600, et al.; GLSEQ, LLC/SCI Technologies. Inc; Hitachi-GE Nuclear Energy, Ltd.; Mitsubishi Heavy Industries, Ltd. (MHI); Toshiba Corporation; Westinghouse Electric Company (American Society of Mechanical Engineers (ASME), United States):