NUCLEAR TECHNIQUES, Volume. 45, Issue 12, 120601(2022)
Research on multi-scale creep behaviors of UN-U 3Si 2 composite fuels
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)
Fig. 5. Schematic diagram of periodic boundary conditions and applied loads for cube-shaped voxels
Fig. 6. Comparison of macroscopic equivalent creep strain with and without irradiation 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
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
Fig. 9. Contribution of dispersed phase and matrix to total creep strain
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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
Category: Research Articles
Received: Apr. 12, 2022
Accepted: --
Published Online: Jan. 3, 2023
The Author Email: DING Shurong (dingshurong@fudan.edu.cn)