Design and analysis of the spent fuel transfer basket for the reprocessing plant
NUCLEAR ENERGY SCIENCE AND ENGINEERING|更新时间:2024-10-25
|
Design and analysis of the spent fuel transfer basket for the reprocessing plant
“In the spent fuel storage pool of the reprocessing plant, a suspended basket is used to store and transport spent fuel components, which enhances the transport capacity and has good safety and economy. A storage and transportation basket capable of loading 8 boxes of spent fuel assemblies at once was designed based on the typical structural parameters of spent fuel assemblies used in commercial nuclear power plants in China. A critical safety analysis was conducted on the storage and transportation basket of fully loaded spent fuel assemblies using SuperMC software, followed by seismic analysis using ANSYS finite element software. The results of the critical safety analysis indicate that even if the basket loaded with spent fuel assemblies is tightly arranged in the infinite spent fuel storage pool, the highest keff of the storage pool is only 0.906; The seismic analysis results show that under a design seismic acceleration of 0.3 g, the maximum structural stress of the suspended basket is 7.92 MPa, and the maximum deformation is 0.32 mm, which does not affect its function. Therefore, the design of the storage and transportation basket is reasonable and can meet the basic safety requirements of the spent fuel pool storage and transportation basket in the reprocessing plant.”
MEI Huaping,YANG Guowei,DUAN Chengjun,et al.Design and analysis of the spent fuel transfer basket for the reprocessing plant[J].NUCLEAR TECHNIQUES,2021,44(05):83-88.
MEI Huaping,YANG Guowei,DUAN Chengjun,et al.Design and analysis of the spent fuel transfer basket for the reprocessing plant[J].NUCLEAR TECHNIQUES,2021,44(05):83-88. DOI: 10.11889/j.0253-3219.2021.hjs.44.050603.
Design and analysis of the spent fuel transfer basket for the reprocessing plant
Experimental and theoretical study on the natural circulation characteristics of humid air in the fuel assembly of a full-scale pressurized water reactor
Geometric configuration of fuel assembly for small lightweight lead-bismuth reactor
Theoretical research on location of fuel assemblies failure using the activity ratio of134Cs and 137Cs
Low pressure distillation technology of molten salt in spent fuel pyroprocessing field
Design of fuel assembly for molten-salt-cooled reactors
Related Author
GU Hanyang
LIU Limin
WANG Xiaowen
NI Song
LIU Maolong
LI Leilei
ZHAO Pengcheng
WANG Weijia
Related Institution
Department of Mechanical Engineering, City University of Hong Kong
School of Nuclear Science and Engineering, Shanghai Jiao Tong University
Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China
School of Nuclear Science and Technology, University of South China