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To Study CFD Analysis of Heat Transfer in the Supercritical Nuclear Reactor Fuel Rod Assemblage with R-12 Coolant


Adarsh Tripathi , Suyash institute of information and Technology, Gorakhpur; Adarsh Tripathi, Suyash institute of information and Technology, Gorakhpur; Shani Kumar, mmmut gorakhpur; Sangam Kumar, Suyash institute of information and Technology, Gorakhpur


CFD, FVM and R-12 as Coolant


The steady state temperature distribution in a nuclear fuel rod using R-12 as coolant has been discussed in this paper. A high amount of energy is released by fission reaction within the nuclear fuel rod. This energy is then transferred by heat conduction to the surface of the fuel rod.. In this work, a model of the equivalent nuclear reactor is prepared in ANSYS design modeler and two particular sub channels are taken. The physical dimensions and the input data required during modeling as well as computation have been taken from an experimental paper; where inlet pressure is 4.63 MPa, inlet temperature is 392 K and heat flux is 33.5kW/m2. Analysis has been done through ANSYS CFD technique to obtain steady state heat transfer in nuclear reactor fuel rod assembly and the local heat transfer coefficient of supercritical R-12 in sub channels of CANDU reactor under cooling conditions which is equivalent to a supercritical water reactor. Hence to confirm the turbulent nature of the flow, Reynolds number variation across the heated length is found out. Later; input conditions such as mass flux, heat flux, and pitch to diameter ratio and inlet pressure are varied to observe its effects on temperature distribution and local heat transfer coefficient. Hence results in the enhancement of heat transfer from the fuel rod cladding surface.

Other Details

Paper ID: IJSRDV4I110100
Published in: Volume : 4, Issue : 11
Publication Date: 01/02/2017
Page(s): 47-53

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