| INORGANIC MATERIALS AND CERAMIC MATRIX COMPOSITES |
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| Performance Analysis of UO2 Fuel Based on MOOSE Platform |
| WANG Zhao1, ZHANG Xinhu2, WANG Zhaohao1, WANG Guan3,4, XI Yongbo2, ZHENG Wei5, DING Yang6, ZHU Libing6, DENG Yongjun5, FU Xiangang5, YUN Di1,7, LIU Wenbo1
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1 School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
2 Nuclear Power Institute of China, Chengdu 610213, China
3 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
4 School of Nuclear Science and Technology, University of Chinese Academy of Sciences, Beijing 100049, China
5 China Nuclear Power Technology Research Institute Co.,Ltd., Shenzhen 518000, Guangdong, China
6 Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China
7 State Key Laboratory of Multi-phase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China |
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Abstract In order to better simulate the physical processes of nuclear fuel radiation swelling, radiation creep, thermal creep, fission gas release, pellet cladding mechanical interaction (PCMI) and other physical processes, as well as the coupling between radiation-heat-force and other physical fields, a performance analysis program for PWR UO2 fuel has been developed based on the multiphysics object-oriented simulation environment (MOOSE) platform. The experimental data of Halden reactor IFA-432r1 and IFA-513r6 rods were used to verify the steady-state and tran-sient performance, and preliminary analysis of fuel performance under the conditions was conducted. The results show that the program deve-loped in this paper can fairly accurately simulate the radiation-thermo-mechanical behavior of fuel rods during reactor operation. Under steady-state operating conditions, periodic stress peaks will appear in the axial direction indicated by the axial cladding strain profile; at the transient, the sudden change in power will cause significant changes in the centerline temperature of the fuel pellet and the contact pressure between pellet and cladding, which can considerably affect the safety of the fuel rod.
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Published:
Online: 2022-04-07
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| Fund:CNNC Nuclear Safety and Advanced Nuclear Energy Technology Leading Innovation Fund. |
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2022, Vol. 36 
