Analysis of Pressurized Water Reactor Fuel Rod Using Nano Fluid

Abstract

The project aims at analysing the flow through a PWR Nuclear Fuel Rod. In this analysis, fuel rod is simulated using ANSYSCFX 14. Fuel Rod is simulated along with the Spacer Grid. The project aims at studying the behaviour of nano fluids under laminar flow conditions and its application as Nuclear reactor coolants. The properties of two nano fluids have been studied-Al₂O₃ and CuO with water as base fluid. Their properties have been then compared with each other as well as under different conditions of flow and along the different regimes of flow. The nano particles are in the form of suspended metallic layer which when mixed with some percentage of water ensures ‘higher thermal conductivity’. Water acts as the base fluid. The Computational Fluid Dynamics (CFD) model for nuclear reactor has been developed and different fluids have been tested for their performance under different conditions. We are focussed in exploring the nuclear applications of nano fluids in the following area of coolant for reactor in PWR, cooling reactor core during emergency of PWR and increase in conductivity of nano fluids with increase in concentration of nano fluids when mixed with coolant.

Keywords: fission, fuel, Computational Fluid Dynamics

Cite this Article

Bhandari Yogesh, Guven Ugur. Analysis of Pressurized Water Reactor Fuel Rod Using Nano Fluid. Journal of Nuclear Engineering and Technology. 2015; 5(3): 14-25p.