Researchers have accounted for fluid-structure interaction (FSI) using different approaches in seismic analysis of spent fuel storage bay (SFSB) of nuclear power plant (NPP), which acts as a provisional onsite storage for spent fuel assemblies/racks which has been used in the nuclear reactor. The major concerns about the spent fuel pool are its ability to prevent the loss of radioactive coolant and thus maintaining cooling of the radioactive fuels. Researchers used different approaches to capture the fluid-structure interaction during the seismic excitation using: (a) Empirical formulation: Researchers have given empirical relationships of sloshing height on the basis of size of tank, height of water in tank but the limitation of these formulations is it will be valid only for standard shape, size of tank, and input acceleration. (b) Experimental studies: Researchers have developed the model of the tank and validated it with actual sloshing height of tank but the limitation of this method is it’s applicable for small scale problem of tanks and not valid for large scale problems of tanks. (c) Numerical analysis: In this method finite element method (FEM) and volume of fluid (VOF) technique is used for finding the sloshing height of tank but the limitation of this method is computational time and accuracy. The outcome of literature review is presented in this paper along with the advantages and disadvantages of all the approach such as empirical formulation, experimental studies, and numerical analysis are presented. This paper adopts Coupled Eulerian and Lagrangian (CEL) analysis technique for modeling fluid-structure interaction, which accounts the limitation of each method stated in the literature. The presented approach is validated by comparing sloshing height with various IS codes formulation. Based on the above approaches, it is concluded that the Coupled Eulerian and Lagrangian (CEL) technique can be used to estimate different hydrodynamic parameters for spent fuel storage bay (SFSB) of nuclear power plant (NPP).

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Fluid-Structure Interaction to Estimate the Sloshing Liquid in Spent Fuel Pool Subjected to Earthquake Loading

  • Rahul K. Shukla,
  • Girish Patil,
  • Kapilesh Bhargava

摘要

Researchers have accounted for fluid-structure interaction (FSI) using different approaches in seismic analysis of spent fuel storage bay (SFSB) of nuclear power plant (NPP), which acts as a provisional onsite storage for spent fuel assemblies/racks which has been used in the nuclear reactor. The major concerns about the spent fuel pool are its ability to prevent the loss of radioactive coolant and thus maintaining cooling of the radioactive fuels. Researchers used different approaches to capture the fluid-structure interaction during the seismic excitation using: (a) Empirical formulation: Researchers have given empirical relationships of sloshing height on the basis of size of tank, height of water in tank but the limitation of these formulations is it will be valid only for standard shape, size of tank, and input acceleration. (b) Experimental studies: Researchers have developed the model of the tank and validated it with actual sloshing height of tank but the limitation of this method is it’s applicable for small scale problem of tanks and not valid for large scale problems of tanks. (c) Numerical analysis: In this method finite element method (FEM) and volume of fluid (VOF) technique is used for finding the sloshing height of tank but the limitation of this method is computational time and accuracy. The outcome of literature review is presented in this paper along with the advantages and disadvantages of all the approach such as empirical formulation, experimental studies, and numerical analysis are presented. This paper adopts Coupled Eulerian and Lagrangian (CEL) analysis technique for modeling fluid-structure interaction, which accounts the limitation of each method stated in the literature. The presented approach is validated by comparing sloshing height with various IS codes formulation. Based on the above approaches, it is concluded that the Coupled Eulerian and Lagrangian (CEL) technique can be used to estimate different hydrodynamic parameters for spent fuel storage bay (SFSB) of nuclear power plant (NPP).