XING Zhong hu, YING Shi hao (Key Lab of Nuclear Fuel and Material, Nuclear Power Institute of China, Chengdu 610041, China). Study on the Irradiation Swelling of U_3Si_2-Al Dispersion Fuel[J]. Atomic Energy Science and Technology, 2001, 35(1): 15-15. DOI: 10.7538/yzk.2001.35.01.0015
Citation: XING Zhong hu, YING Shi hao (Key Lab of Nuclear Fuel and Material, Nuclear Power Institute of China, Chengdu 610041, China). Study on the Irradiation Swelling of U_3Si_2-Al Dispersion Fuel[J]. Atomic Energy Science and Technology, 2001, 35(1): 15-15. DOI: 10.7538/yzk.2001.35.01.0015
  • The dominant modeling mechanisms on irradiation swelling of U 3Si 2 Al dispersion fuel are introduced. The core of dispersion fuel is looked to as micro fuel elements of continuous matrix. The formation processes of gas bubbles in the fuel phase are described through the behavior mechanisms of fission gases. The swelling in the fuel phase causes the interaction between fuel particles and metal matrix, and the metal matrix can restrain the irradiation swelling of fuel particles. The developed code can predict irradiation swelling values according to the parameters of fuel elements and irradiation conditions, and the predicted values are in agreement with the measured results.
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