A CFD Analysis of Hydraulic Characteristics of the Rod Bundles in the BREST-OD-300 Wire-Spaced Fuel Assemblies

Authors: Dmitry V. Fomichev, Vladimir I. Solonin

Abstract:

This paper presents the findings from a numerical simulation of the flow in 37-rod fuel assembly models spaced by a double-wire trapezoidal wrapping as applied to the BREST-OD-300 experimental nuclear reactor. Data on a high static pressure distribution within the models, and equations for determining the fuel bundle flow friction factors have been obtained. Recommendations are provided on using the closing turbulence models available in the ANSYS Fluent. A comparative analysis has been performed against the existing empirical equations for determining the flow friction factors. The calculated and experimental data fit has been shown.

An analysis into the experimental data and results of the numerical simulation of the BREST-OD-300 fuel rod assembly hydrodynamic performance are presented.

Keywords: BREST-OD-300, ware-spaces, fuel assembly, computation fluid dynamics.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1094180

References:

[1] The White Book of Nuclear Energy / V.V. Orlov, M.M. Seliverstov, V.A. Tishchenko, V.V. Uzhanova, V.S. Smirnov, I.Kh. Ganev, A.V. Lopatkin, S.V. Bryunin, A.N. Karhov, S.V. Yevropin, G.Ye. Shatalov, V.Ye. Sitnikov, P.I. Dolgosheev V.B. Kozlov, V.P. Fotin; ed. By Ye.O. Adamov. - M.: NIKIET Publishers, 1998. – 356 p. (in Russian).
[2] Yu.G. Dragunov. Technical Solutions and Development Phases of the BREST-OD-300 Reactor Facility / Yu.G. Dragunov, V.V. Lemekhov, V.S. Smirnov, N.G. Chernetsov // J. Atomnaya Energiya.- 2012.- V. 113. No. 1. P. 58-64. (in Russian).
[3] A.V. Sheynina. Hydraulic Resistance of Rod Bundles in an Axial Fluid Flow / А.V. Sheynina // Liquid Metals: collected works.- M.: Atomizat, 1967. P. 210-223. (in Russian).
[4] A.V. Zhukov. An Analysis into the Hydraulic Resistance in Fuel Bundles of Fast-Neutron Reactors / A.V. Zhukov, A.P. Sorokin, P.A. Titov, P.A. Ushakov // J. Atomnaya Energiya.- 1986. V. 60. No. 5. P. 317-321. (in Russian).
[5] Bubelis, E. Review and Proposal for Best-fit of Wire-wrapped Fuel Bundle Friction Factor and Pressure Drop Predictions Using Various Existing Correlations / E. Bubelis, M. Schikorr.- Forschungszentrum Karlsruhe GmbH.- Karlsruhe, 2008.- 61 p.
[6] Turbulent Flow and Heat Transfer in Channels of Power Plants / B.V. Dzyubenko, A. Sakalauskas, L. Ashmantas, M.D. Segal. - Vilnius: Pradai, 1995. – 300 p. (in Russian).
[7] Reference Book on Thermohydraulic Calculations in Nuclear Power. Thermohydraulic Processes in NPPs / P.L. Kirillov, V.P. Bobkov, A.V. Zhukov, Yu.S. Yuryev; ed. by P.L. Kirillov.- М.: IzdAt, 2010.- 776 p. (in Russian).
[8] ANSYS FLUENT, Theory Guide, Rel. 14.5.- ANSYS Inc., 2012.
[9] ANSYS Meshing User’s Guide, Rel. 14.5.- ANSYS Inc., 2012.
[10] Launder, B. E. Lectures in Mathematical Models of Turbulence / B. E. Launder, D. B. Spalding.- London, England: Academic Press, 1972.
[11] A.Yu. Snegiryov. High-Performance Computing in Engineering Physics. Numerical Simulation of Turbulent Flows: a textbook / A.Yu. Snegiryov.- SPb.: Polytechnic University Publishing House, 2009.- 143 p. (in Russian).
[12] Orszag, S. A. Renormalization Group Modeling and Turbulence Simulations / S.A. Orszag, V. Yakhot, W.S. Flannery, F. Boysan, D. Choudhury, J. Maruzewski, B. Patel // International Conference on Near-Wall Turbulent Flows / Tempe, Arizona, 1993.
[13] Shih, T.-H. A New Eddy-Viscosity Model for High Reynolds Number Turbulent Flows - Model Development and Validation / T.-H. Shih, W.W. Liou, A. Shabbir, Z. Yang, and J. Zhu // Computers Fluids. 1995. No. 24 (3). P. 227-238.
[14] Gibson, M.M. Ground Effects on Pressure Fluctuations in the Atmospheric Boundary Layer / M. M. Gibson, B. E. Launder. // J. Fluid Mech. 1978. No. 86. P. 491-511.
[15] Launder, E. Progress in the Development of a Reynolds-Stress Turbulence Closure / E. Launder, G.J. Reece, W. Rodi // J. Fluid Mech. 1975. No. 68 (3). P. 537–566.
[16] Spalart, P. A One-Equation Turbulence Model for Aerodynamic Flows / P. Spalart, S. Allmaras // American Institute of Aeronautics and Astronautics.- Technical Report AIAA-92-0439.- 1992.
[17] Wilcox, D.C. Turbulence Modeling for CFD / D.C. Wilcox.- DCW Industries, Inc. La Canada, California, 1998.- 460 p.
[18] Menter, F.R. Two-Equation Eddy-Viscosity Turbulence Models for Engineering Applications / F.R. Menter // AIAA Journal. 1994, No. 32 (8).- pp. 1598-1605.
[19] Menter, F.R. Ten Years of Experience with the SST Turbulence Model / F. R. Menter, M. Kuntz, R. Langtry // Turbulence, Heat and Mass Transfer. 2003, No. 4. P. 625-632.
[20] Bradshaw, P. Calculation of Boundary Layer Development Using the Turbulent Energy Equation / P. Bradshaw, D.H. Ferriss, N.P. Atwell // J. Fluid Mech. 1967. No. 28. P. 593-616.
[21] Launder, B.E. The Numerical Computation of Turbulent Flows / B.E. Launder, D.B. Spalding // Computer Methods in Applied Mechanics and Engineering. 1974. No. 3. P. 269-289.
[22] Bishop, A. Hydraulic Characteristics of Wire-Wrapped Rod Bundles / A. Bishop, N. Todreas // Nuclear Engineering and Design. 1980. No. 62 (1-3). P. 271-293.
[23] Cheng, S.K. Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal Rod Bundles - Bundle Friction Factors, Sub-channel Friction Factors and Mixing Parameters / S.K. Cheng, N.E. Todreas // Nuclear Engineering and Design. 1986. No. 92. pp. 227-251.
[24] Sobolev, V. Fuel Rod and Assembly Proposal for XT-ADS Pre-design / V. Sobolev // Coordination meeting of WP1&WP2 of DM1 IP EUROTRANS / Bologna, 8-9 February, 2006.
[25] Guidelines, Rules, Methods of Calculation of Hydrodynamic and Thermal Characteristics of the Components and Equipment of Power Plants. Steering Technical Material: in 3 vols. / Obninsk, 1991. - V. 1. – 435 p. (in Russian).
[26] Engel, F. C. Laminar, Transition and Turbulent Parallel Flow Pressure Drop across Wire-Wrap-Spaced Rod Bundles / F.C. Engel, et al // Nuclear Science and Engineering. 1979. V. 69, pp. 290-296.
[27] Rehme, K. Pressure Drop Correlations for Fuel Element Spacers / K. Rehme // Nuclear Technology. 1973. V. 17. pp. 15-23.
[28] Novendstern, E.H. Turbulent Flow Pressure Drop Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System / E.H. Novendstern // Nuclear Engineering and Design. 1972. V. 22, pp. 19-27.