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Flow and Convective Heat Transfer Analysis Using RANS for A Wire-Wrapped Fuel Assembly  

Ahmad, Imteyaz (Department of Mechanical Engineering, Inha University)
Kim, Kwang-Yong (Department of Mechanical Engineering, Inha University)
Publication Information
Journal of Mechanical Science and Technology / v.20, no.9, 2006 , pp. 1514-1524 More about this Journal
Abstract
This work presents the three-dimensional analysis of flow and heat transfer performed for a wire-wrapped fuel assembly of liquid metal reactor using Reynolds-averaged Wavier-Stokes analysis in conjunction with 557 model as a turbulence closure. The whole fuel assembly has been analyzed for one period of the wire-spacer using periodic boundary conditions at inlet and outlet of the calculation domain. Three different assemblies, two 7-pin wire-spacer fuel assemblies and one bare rod bundle, apart from the pressure drop calculations for a 19-pin case, have been analyzed. Individual as well as a comparative analysis of the flow field and heat transfer have been discussed. Also, discussed is the position of hot spots observed in the wire-spacer fuel assembly. The flow field in the subchannels of a bare rod bundle and a wire-spacer fuel assembly is found to be different. A directional temperature gradient is found to exist in the subchannels of a wire-spacer fuel assembly Local Nusselt number in the subchannels of wire-spacer fuel assemblies is found to vary according to the wire-wrap position while in case of bare rod bundle, it's found to be constant.
Keywords
Wire-Spacer; Liquid Metal Reactor; RANS Analysis; Heat Transfer; Fuel Assembly;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
Times Cited By Web Of Science : 6  (Related Records In Web of Science)
Times Cited By SCOPUS : 9
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1 Khan, E. D., Rohsenw, W. M., Sonin, A. A. and Todreas, N. E., 1975, 'A Porous Body Model for Predicting Temperature Distribution in Wire-Wrapped Fuel Rod Assemblies,' Nuclear Engineering and Design, Vol. 35, pp. 1-12   DOI   ScienceOn
2 Han, G. Y., 2000, 'A Mathematical Model for the Thermal-Hydraulic Analysis of Nuclear Power Plants,' Int. Comm. Heat Mass Transfer, Vol. 27, pp. 795-805   DOI   ScienceOn
3 Ha, K. S., Jeong, H. Y., Chang, W. P., Kwon, Y. M. and Lee, Y. B., 2004, 'Wire-Wrap Models for Subchannel Blockage Analysis,' Journal of the Korean Nuclear Society, Vol. 36, pp. 165-174   과학기술학회마을
4 Menter, F. and Esch, T., 2001, 'Elements of Industrial Heat Transfer Predictions,' 16th Bazilian Congress of Mechanical Engineering (CPBEM), Uberlandia, Brazil
5 Fontana, M. H., 1973, 'Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM-2A),' ORNL-4852, Oak Ridge National Laboratory
6 Takase, K., 1995, 'Experimental and Analytical Studies on Turbulent heat Transfer Performance of a Fuel Rod with Spacer Ribs for High Temperature Gas-Cooled Reactors,' Nuclear Engineering and Design, Vol. 154, pp. 345-356   DOI   ScienceOn
7 Yang, W. S., 1997, 'An LMR Core ThermalHydraulics Code Based on the ENERGY Model,' J. of Korean Nuclear Society, Vol. 29, p.406
8 Roidt, R. M., Carelli, M. D. and Markley, R. A., 1980, 'Experimental Investigations of the Hydraulic Field in Wire-Wrapped LMFBR core Assemblies,' Nuclear Engineering and Design, Vol. 62, pp. 295-321   DOI   ScienceOn
9 Sha, W. T., 1980, 'An overview on Rod-Bundle Thermal-Hydraulic Analysis,' Nuclear Engineering and Design, Vol. 62, pp. 1-24   DOI   ScienceOn
10 Rehme, K. and Trippe, G., 1980, 'Pressure Drop and Velocity Distribution in Rod Bundles with Spacer Grids,' Nuclear Engineering and Design, Vol. 62, pp. 349-359   DOI   ScienceOn
11 Patankar, S. V., 1980, Numrical Heat Transfer and Fluid Flow, Hemisphere, Washington DC
12 CFX-5.7 Solver Theory,2004, Ansys Inc.
13 Engel, F. C., Minushkin, B., Atkins, R. J. and Markley, R. A., 1980, 'Characterization of Heat Transfer and Temperature Distribution in an Electrically Heated Model of an LMFBR Blanket Assembly,' Nuclear Engineering and Design, Vol. 62, pp. 335-347   DOI   ScienceOn
14 Madni, I. K. and Agarwal, A. K., 'LMFBR System Analysis: Impact of Heat Transport System on Core Thermal-Hydraulics,' Nuclear Engineering and Design, Vol. 62, pp. 199-218   DOI   ScienceOn
15 Cui, X. Z. and Kim, K. Y., 2003, 'Three Dimensional Analysis of Turbulent Heat Transfer and Flow Through Mixing Vane in a Subchannel of Nuclear Reactor,' Journal of Nuclear Science and Techonology, Vol. 40, No. 10, pp. 719-724   DOI   ScienceOn
16 Coffield, R. D. and Markley, R. A., 1980, 'Natural Convection Analysis and Verification for LMFBR Cores,' Nuclear Engineering and Design, Vol. 62, pp. 181-198   DOI   ScienceOn
17 Kim, W. S. et at., 2002, 'A Subchannels Analysis Code MATRA-LMR for Wire Wrapped LMR Subassembly,' Annals of Nuclear Energy, Vol. 29, 3003-321-2002   DOI   ScienceOn
18 Macdougall, J. D. and Lillington, J. N., 1984, 'The SABRE Code for Fuel Rod Cluster Thermohydraulics,' Nuclear Engineering and Design, Vol. 82, pp. 91-407   DOI   ScienceOn
19 Chun, M. H. and K. W. Seo, 2001, 'An Experimental Study and Assessment of Existing Friction Factor Correlations for Wire-Wrapped Fuel Assemblies,' Annals of Nuclear Energy, Vol. 28, pp. 1683-1695   DOI   ScienceOn
20 Choi, S. K., Choi, K., Nam, H. Y., Choi, J. H. and Choi, H. K., 2003, 'Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor,' Journal of Pressure Vessel Technology, Vol. 125   DOI   ScienceOn
21 Cheng, S. K. and Todreas, N. E., 1986, 'Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal rod Bundles- Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters,' Nuclear Engineering and Design, Vol. 92, pp. 227-251   DOI   ScienceOn
22 Incropera, F. P. and DeWitt, D. P., 2002, Heat and Mass Transfer (Fifth Edition), John Wiley and Sons, Inc., p. 493
23 Kim, K. Y. and Seo, J. W., 2005, 'Numerical Optimization for The Design of A Spacer Grid with Mixing Vane in A Pressurized Water Reactor Fuel Assembly,' Nuclear Technology, Vol. 149, pp.62-70
24 Kim, H. M. and Kim, K. Y., 2004, 'Design Optimization of Rib-Roughened Channel to Enhance Turbulent Heat Transfer,' International Journal of Heat and Mass Transfer, Vol. 47, pp. 5159-5168   DOI   ScienceOn
25 Khan, E. D., Rohsenw, W. M., Sonin, A. A. and Todreas, N. E., 1975, 'A Porous Body Model for Predicting Temperature Distribution in Wire-Wrapped Fuel Rod Assemblies Operating in Combined Forced and Free Convection,' Nuclear Engineering and Design, Vol. 35, pp. 199-211   DOI   ScienceOn