|

Pin Bundles Hydraulic Characteristics of the BREST-OD-300 Wire-Spaced Fuel Subassemblies

Authors: Fomichev D.V., Solonin V.I. Published: 15.04.2015
Published in issue: #2(101)/2015  

DOI: 10.18698/0236-3941-2015-2-4-17

 
Category: Power Engineering | Chapter: Nuclear Power Plants, Fuel Cycle, Radiation Safety  
Keywords: experimental nuclear reactor, wire-spaced fuel subassembly, computational fluid dynamics

Findings from numerical simulation of the flow in 37-rod fuel assembly model spaced by a double-wire tapered wrapping as applied to the BREST-OD-300 reactor plant, are presented. Data on a static pressure heightwise distribution within the dummies, and dependencies for determining the fuel bundle flow friction factors are obtained. Recommendations are provided on using the closing turbulence models available in the ANSYS Fluent CFD package. A comparative analysis is performed against the existing empirical dependencies for determining the flow friction factors. The calculated and experimental data compliance is demonstrated. Analysis of the experimental data as well as the numerical simulation results for hydrodynamic performance of the BREST-OD-300 fuel rod assembly are presented.

References

[1] Orlov V.V., Seliverstov M.M., Tishchenko V.A., Zhanova V.U., Smirnov V.S., Ganev I.H., Lopatkin A.V., Bryunin S.V., Karhu A.N., Evropin S.V., Shatalov G.E., Sitnikov V.E., Dolgosheev P.I. Kozlov V.B., Photinus V.P., ed. Adamov E.O. The White Book of Nuclear Energy. Moscow, GUPNIKIET Publ., 1998. 356 p.

[2] Dragunov Yu.G.,Lemekhov V.V., Smirnov V.S., Chernetsov N.G. The Technical Solutions and Development Phases of the Reactor Plant BREST-OD-300.AtomicEnergyJ., 2012, vol. 113, no. 1, pp. 58-64 (in Russ.).

[3] Sheinina A.V. Hydraulic resistance of rod bundles in an axial fluid flow. Liquid Metals, 1967, pp. 210-223 (in Russ.).

[4] Zhukov A.V., Sorokin A.P., Titov P.A., Ushakov P.A. Analysis of the hydraulic resistance of the fast reactor fuel bundles. Atomic Energy J., 1986, vol. 60, no. 5, pp. 317-321(in Russ.).

[5] Bubelis E.,Schikorr M. Review and proposal for best-fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations. Forschungszentrum Karlsruhe GmbH., Karlsruhe, 2008. 61 p.

[6] Dziubienko B.V., Sakalauskas A., Ashmantas L., Siehal M.D. Turbulent flow and heat transfer in channels of power plants. Vilnius,PradaiPubl., 1995. 300 p.

[7] Kirillov P.L., Bobkov V.P., Zhukov A.V., Yur’yev Yu.S., ed. Kirillov P.L. The Reference Thermohydraulic Calculations in Nuclear Power.Thermohydraulic Processes in the NPPMoscow, AtPubl., 2010. 776 p.

[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.,Spalding D.B. Lectures in Mathematical Models of Turbulence.London, England, Academic Press, 1972.

[11] Snegiryov A.Yu. High-Performance Computing in Technical Physics.Numerical Simulation of Turbulent Flows. S. Petersburg, Polytechnic University Publ., 2009. 143 p.

[12] Orszag S.A., Yakhot V., Flannery W.S., Boysan F., Choudhury D., Maruzewski J., Patel B. Renormalization Group Modeling and Turbulence Simulations. International Conference on Near-Wall Turbulent Flows. Tempe, Arizona, 1993.

[13] Shih, T.-H., Liou W.W., Shabbir A., Yang Z., Zhu J. A New Eddy-Viscosity Model for High Reynolds Number Turbulent Flows - Model Development and Validation. Computers Fluids, 1995, no. 24 (3), pp. 227-238.

[14] Gibson M.M., Launder B.E. Ground Effects on Pressure Fluctuations in the Atmospheric Boundary Layer. J. Fluid Mech., 1978, no. 86, pp. 491-511.

[15] Launder E., Reece G.J., Rodi W. Progress in the Development of a Reynolds-Stress Turbulence Closure. J. Fluid Mech., 1975, no. 68 (3), pp. 537-566.

[16] Spalart P., Allmaras S. A one-equation turbulence model for aerodynamic flows. American Institute of Aeronautics and Astronautics. Technical Report AIAA-92-0439. 1992.

[17] Wilcox D.C. Turbulence Modeling for CFD. DCW Industries, Inc. La Canada, California, 1998. 460 p.

[18] Menter F.R. Two-Equation Eddy-Viscosity Turbulence Models for Engineering Applications AIAA Journal., 1994, no. 32 (8), pp. 1598-1605.

[19] Menter F.R., Kuntz M., Langtry R. Ten Years of Experience with the SST Turbulence Model. Turbulence, Heat and Mass Transfer, 2003, no. 4, pp. 625-632.

[20] Bradshaw P., Ferriss D.H., Atwell N.P. Calculation of boundary layer development using the turbulent energy equation. J. Fluid Mech., 1967, no. 28, pp. 593-616.

[21] Launder B.E., Spalding D.B. The Numerical Computation of Turbulent Flows. Computer Methods in Applied Mechanics and Engineering, 1974, no. 3, pp. 269-289.

[22] Bishop A., Todreas N. Hydraulic characteristics of wire-wrapped rod bundles. Nuclear Engineering and Design, 1980, no. 62 (1-3), pp. 271-293.

[23] Cheng S.K., Todreas N. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-bundle friction factors, sub-channel friction factors and mixing parameters. Nuclear engineering and design, 1986, no. 92, pp. 227-251.

[24] Sobolev V. Fuel Rod and Assembly Proposal for XT-ADS Pre-design. 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 vol. Obninsk, 1991, vol. 1. 435 p.

[26] Engel F.C., et al. Laminar, transition and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles.Nuclear science and engineering, 1979, no. 69, pp. 290-296.

[27] Rehme K. Pressure drop correlations for fuel element spacers. Nuclear technology, 1973, no. 17, pp. 15-23.

[28] Novendstern E.H. Turbulent flow pressure drop model for fuel rod assemblies utilizing a helical wire-wrap spacer system.Nuclear Engineering and Design, 1972, no. 22, pp. 19-27.