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Study of Temperature Distribution in Coolant Channel of Nuclear Power with Fuel Cylinder Element Using Fluent Software

Authors: Elham Zamiri


In this research, we have focused on numeral simulation of a fuel rod in order to examine distribution of heat temperature in components of fuel rod by Fluent software by providing steady state, single phase fluid flow, frequency heat flux in a fuel rod in nuclear reactor to numeral simulation. Results of examining different layers of a fuel rod consist of fuel layer, gap, pod, and fluid cooling flow, also examining thermal properties and fluids such as heat transition rate and pressure drop. The obtained results through analytical method and results of other sources have been compared and have appropriate correspondence. Results show that using heavy water as cooling fluid along with few layers of gas and pod have the ability of reducing the temperature from above 300 C to 70 C. This investigation is developable for any geometry and material used in the nuclear reactor.

Keywords: Nuclear fuel fission, numberal simulation, fuel rod, reactor, fluent software.

Digital Object Identifier (DOI):

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[1] H. Aminifar, M. Mohammadi Pourfar, “heat transfer analysis in fuel rod of nuclear power plant.”, University of Tabriz Magazine, Mechanic engineering, Volume 32, Number 2, 1384.
[2] A. Fentiman, “Nuclear Power Past, Present, and Future,” Purdue University, 2012.
[3] The history of nuclear energy, DOE, NE-008.
[4] Overview of Nuclear Reactor Systems and Fundamentals.
[5] U.S. Energy Information Administration (EIA). New Reactor .Design.
[6] S. Place “Nuclear Reactor Types” An Environment & Energy FactFile provided by the IEE, 2005.
[7] Types of Nuclear Reactors, Institute for Energy and Environmental Research Celebrating 25 years of science for democracy.
[8] T. Pekdemir, T. W. Davies, L. E. Haseler, A. D. Diaper, “Flow distribution on the shell side of a cylindrical shell and tube heat exchanger”, Int. J. Heat and Fluid Flow, 14(1),1993.
[9] T. Pekdemir, T. W. Davies, L. E. Haseler, A. D. Diaper, “Pressure Drop Measurements on the Shell Side of a Cylindrical Shell-and-Tube Heat Exchanger”, J. of heat transfer engineering,15(3).1994.
[10] S. Wang, J. Wen, Y. Li, “An experimental investigation of heat Transfer enhancement for a shell-and-tube heat exchanger”, J. of Applied Thermal Engineering,29,2433-2438, 2009.
[11] U. C. Kapale, S. Chand, “Modeling for shell-side pressure drop for liquid flow in shell-and-tube heat exchanger”, International Journal of Heat and Mass Transfer,49:601-610, 2006.
[12] F. Vera-Garcia, J. R. Garcia-Cascales, J. Gonzalvez-Macia, R. Cabello, R. Llopis, D. Sanchez, E. Torrella, “A simplified model for shell-and-tubes heat exchangers: Practical application”, J. of Applied Thermal Engineering, 30, 1231-1241,2010.
[13] E. Ozden, I. Tari, “Shell side CFD analysis of a small shelland- tube heat exchanger, J. of Energ y Conversion and Management ,51,1004-1014,2010.
[14] Araz Sarchami, Investigation of Thermal Hydraulics of a Nuclear Reactor Moderator, PhD thesis, Mechanical and Industrial Engineering Department University of Toronto, 2011.
[15] Amir Z. Mesquita1, Daniel A. P. Palma2, Antonella L. Costa3, Claubia, Pereira3 Maria A,.F Veloso3.F. . and Patrícia A L. Reis3, Experimental, Distribution of Coolant of in the IPR-R1 Triga NuclearReacto r Core, International Nuclear Atlantic Conference- INAC2011, Belo Horizonte, MG , Brazil, October24-28, 2011.
[16] R. Shinha, I. Dulera, Carbon based materials- application in high temperature nuclear reactors ,Inidian Journal of engineering & materials engineering & Sciences , Vol.17 (2010 ), pp.321-326.
[17] C. A. Adjei, A. G. Ayensu, E. H. K. Akaho, F. K. Quashie, A. B. Asumadu-Sakyi and E. O. “Amartey, Equalisation of Transient Temperature Profile Within the Fuel Pin of a Miniature. Neutron Source Reactor (MNSR) During Total Loss of Coolant,” Research Journal of Applied Sciences, Engineering and Technology, vol. 2(2010), PP 661-668.