• NUCLEAR TECHNIQUES
  • Vol. 45, Issue 12, 120601 (2022)
Qingfeng YANG1, Zhexiao XIE2, Ping CHEN1, Jing ZHANG2, Shixin GAO1, Guochen DING2, Yi ZHOU1, Chunyu YIN1, Shurong DING2、*, Liang HE1, and Dan SUN1
Author Affiliations
  • 1Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
  • 2Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University, Shanghai 200433, China
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    DOI: 10.11889/j.0253-3219.2022.hjs.45.120601 Cite this Article
    Qingfeng YANG, Zhexiao XIE, Ping CHEN, Jing ZHANG, Shixin GAO, Guochen DING, Yi ZHOU, Chunyu YIN, Shurong DING, Liang HE, Dan SUN. Research on multi-scale creep behaviors of UN-U 3Si 2 composite fuels[J]. NUCLEAR TECHNIQUES, 2022, 45(12): 120601 Copy Citation Text show less
    Comparison of the calculated and experimental values of the UN creep model (a) and the U3Si2 creep model (b) (color online)
    Fig. 1. Comparison of the calculated and experimental values of the UN creep model (a) and the U 3Si 2 creep model (b) (color online)
    Microstructure of UN-U3Si2 composite fuel pellets
    Fig. 2. Microstructure of UN-U 3Si 2 composite fuel pellets
    Flowchart diagram of random distribution modeling
    Fig. 3. Flowchart diagram of random distribution modeling
    Schematic diagram of random distribution model
    Fig. 4. Schematic diagram of random distribution model
    Schematic diagram of periodic boundary conditions and applied loads for cube-shaped voxels
    Fig. 5. Schematic diagram of periodic boundary conditions and applied loads for cube-shaped voxels
    Comparison of macroscopic equivalent creep strain with and without irradiation swelling
    Fig. 6. Comparison of macroscopic equivalent creep strain with and without irradiation swelling
    Von Mises stress contourplots (section view) at the fission density of 4.32×1027 fissions·m-3 (a) With radiation swelling, (b) Without radiation swelling
    Fig. 7. Von Mises stress contourplots (section view) at the fission density of 4.32×1027 fissions·m-3 (a) With radiation swelling, (b) Without radiation swelling
    Equivalent creep contour plots (section view) at the fission density of 4.32×1027 fissions·m-3 (a) With radiation swelling, (b) Without radiation swelling
    Fig. 8. Equivalent creep contour plots (section view) at the fission density of 4.32×1027 fissions·m-3 (a) With radiation swelling, (b) Without radiation swelling
    Contribution of dispersed phase and matrix to total creep strain
    Fig. 9. Contribution of dispersed phase and matrix to total creep strain
    Proportions of different creep contribution
    Fig. 10. Proportions of different creep contribution
    Qingfeng YANG, Zhexiao XIE, Ping CHEN, Jing ZHANG, Shixin GAO, Guochen DING, Yi ZHOU, Chunyu YIN, Shurong DING, Liang HE, Dan SUN. Research on multi-scale creep behaviors of UN-U 3Si 2 composite fuels[J]. NUCLEAR TECHNIQUES, 2022, 45(12): 120601
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