| METALS AND METAL MATRIX COMPOSITES |
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| Improvement of Metal Fuel Irradiation Model on Porosity and Development of Metal Fuel Performance Analysis Code for Fast Neutron Reactor |
| WANG Ting1, GAO Yedong1,2, YUN Di1,3, WANG Guan4,5, ZHOU Yi2, ZHANG Kun2, GUO Zixuan2, LYU Liangliang2
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1 School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an 710049, China
2 Nuclear Power Institute of China, Chengdu 610213, China
3 State Key Laboratory of Multi-phase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
4 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
5 University of Chinese Academy of Sciences, Beijing 100049, China |
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Abstract With the development of sodium-cooled fast reactors and lead-cooled fast reactors, the application prospect of metal fuel has initially appeared. The development of metal fuel performance analysis code suitable for sodium-cooled fast reactors is of great significance to the development and application of metal fuels. After investigating and summarizing the influence of the porosity of the pellet on the thermal conductivity and mechanical properties, a new model of the thermal conductivity and mechanical properties of the pellet is proposed. In addition, the heat transfer model and mechanical model were improved after referring to other radiation behavior models of metal fuel in related literatures, a fuel performance analysis code suitable for sodium-cooled fast reactor rod metal fuels was developed using FORTRAN-90. This code can be used to predict typical irradiation behaviors of metal fuels.
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Published:
Online: 2022-06-09
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2022, Vol. 36 
