Browse > Article
http://dx.doi.org/10.3795/KSME-B.2007.31.8.663

Shape Optimization of LMR Fuel Assembly Using Radial Basis Neural Network Technique  

Raza, Wasim (인하대학교 대학원 기계공학과)
Kim, Kwang-Yong (인하대학교 기계공학과)
Publication Information
Transactions of the Korean Society of Mechanical Engineers B / v.31, no.8, 2007 , pp. 663-671 More about this Journal
Abstract
In this work, shape optimization of a wire-wrapped fuel assembly in a liquid metal reactor has been carried out by combining a three-dimensional Reynolds-averaged Navier-Stokes analysis with the radial basis neural network method, a well known surrogate modeling technique for optimization. Sequential Quadratic Programming is used to search the optimal point from the constructed surrogate. Two geometric design variables are selected for the optimization and design space is sampled using Latin Hypercube Sampling. The optimization problem has been defined as a maximization of the objective function, which is as a linear combination of heat transfer and friction loss related terms with a weighing factor. The objective function value is more sensitive to the ratio of the wire spacer diameter to the fuel rod diameter than to the ratio of the wire wrap pitch to the fuel rod diameter. The optimal values of the design variables are obtained by varying the weighting factor.
Keywords
Liquid Metal Reactor; Wire Spacer; Shape Optimization; Neural Network; Reynolds-Averaged Navier-Stokes Equations;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
Times Cited By SCOPUS : 2
연도 인용수 순위
1 Kim, W.S., Kim, Y.G. and Kim, Y.J., 2002, 'A Subchannels Analysis Code MATRA-LMR for Wire Wrapped LMR Subassembly,' Annals of Nuclear Energy. 29, 303-321   DOI   ScienceOn
2 Ahmad, I. and Kim, K.Y., 2006, Flow and Convective Heat Transfer Analysis Using RANS for a Wire-Wrapped Fuel Assembly, Journal of Mechanical Science and Technology. 20, 1514-1524   과학기술학회마을   DOI   ScienceOn
3 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, 149, 62-70   DOI
4 Papila, N., Shyy, W., Griffin ,L. W. and Dorney, D. J., 'Shape Optimization of Supersonic Turbines Using Responses Surface and Neural Network Methods,' Journal of Propulsion and Power, Vol. 18, No. 3, 2002, pp. 509-518   DOI   ScienceOn
5 Vaidyanathan, R., Papila, N., Shyy, W., Tucker, K. P., Griffin, L. W., Haftka, R. T. and Fitz-Coy, N., 'Neural Network and Response Surface Methodology for Rocket Engine Component Optimization,' 8th AIAA/USAF/NASA/ISSMO Symposium on Multidisciplinary Analysis and Optimization, Paper No. 2000-4480, Long Beach, CA,2000
6 Menter, F.R., 1994, 'Two-equation Eddy-Viscosity Turbulence Models for Engineering Applications,' AIAA J. 32, 1598-1605   DOI   ScienceOn
7 Incropera, F.P. and Dewitt, D.P., 2002, 'Heat and Mass Transfer (Fifth Edition),' John Wiley and Sons, Inc., p. 493
8 MATLAB${\circledR}$, The Language of Technical Computing, Release 14. The MathWorks Inc
9 Fernandez, E. F. and Carajilescov, P., 1999, 'Model for Subchannel Friction Factors and Flow Redistribution in Wire-Wrapped Rod Bundles,' Journal of the Brazilian Society of Mechanical Sciences, 21, doi: 10.1590/S01 00-73861999000400003   DOI
10 CFX-5.7 Solver Theory, 2004. Ansys Inc
11 Roidt, R.M., Carelli, M.D. and Markley, R.A., 1980, 'Experimental Investigations of the Hydraulic Field in Wire-Wrapped LMFBR Core Assemblies,' Nucl. Eng. Des. 62, 295-321   DOI   ScienceOn
12 Chun, M.H. and Seo, K.W., 2001, 'An Experimental Study and Assessment of Existing Friction Factor Correlations For Wire-Wrapped Fuel Assemblies,' Annals of Nuclear Energy, 28, 1683-1695   DOI   ScienceOn
13 Khan, E.U., 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,' Nucl. Eng. Des. 35, 1-12   DOI   ScienceOn
14 Yang, W. S., 1997, An LMR Core Thermal-Hydr aulics Code Based on the ENERGY Model. J. of Korean Nuclear Society. 29, 406   과학기술학회마을
15 McKay, M.D., Beckman, R.J. and Conover, W.J., 1979, 'A Comparison of Three Methods for Selecting Values of Input Variables in the Analysis of Output from a Computer Code,' Technometrics. 21, 239-245   DOI
16 Macdougall, J.D. and Lillington, J.N., 1984, 'The SABRE Code for Fuel Rod Cluster Thermohydraulics,' Nucl. Eng. Des. 82, 91-407   DOI   ScienceOn
17 Bardina, J.E., Huang, P.G.. and Coakley, T., 1997, 'Turbulence Modeling Validation,' AIAA Paper 97-2121
18 Incropera, F.P. and Dewitt, D.P., 2002, 'Heat and Mass Transfer (Fifth Edition),' John Wiley and Sons, Inc., p. 493
19 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
20 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,' Nucl. Eng. Des. 62, 335-347   DOI   ScienceOn
21 Fernandez, E. F. and Carajilescov, P., 2000, 'Static Pressure and Wall Shear Stress Distributions in Air Flow in a Seven Wire-Wrapped Rod Bundle,' Journal of the Brazilian Society of Mechanical Sciences, 22, doi: 10.1590/S0100-73862000000200012   DOI
22 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. 125, 233-238   DOI   ScienceOn