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http://dx.doi.org/10.3795/KSME-B.2017.41.1.053

Examination of Forced Convection Heat Transfer Performance of a Twist-Vane Spacer Grid for a Dual-Cooled Annular Fuel Assembly  

Lee, Chi Young (Dept. of Fire Protection Engineering, Pukyong Nat'l Univ.)
Publication Information
Transactions of the Korean Society of Mechanical Engineers B / v.41, no.1, 2017 , pp. 53-62 More about this Journal
Abstract
The forced convection heat transfer performance of a twist-vane spacer grid for a dual-cooled annular fuel assembly was examined experimentally. The twist-vane spacer grid was uniquely designed to enhance mixing inside subchannels and mixing between adjacent subchannels. For testing, a $4{\times}4$ square-arrayed rod bundle with narrow gaps between rods was prepared as the dual-cooled annular fuel assembly to be simulated. The pitch-to-rod diameter ratio of simulated dual-cooled annular fuel assembly was 1.08. The experiments were performed under the following conditions: axial bulk velocity, 1.5 m/s and heat flux, $26kW/m^2$. With regard to the circumferential temperature distribution, the lowest rod-wall temperatures upstream and downstream were measured at the subchannel center and the position toward the tip of twist-vane, respectively. With regard to the axial temperature distribution, behind the twist-vane spacer grid, the rod-wall temperature decreased drastically, and the Nusselt number was enhanced by up to 56 %. The present measured data indicate that the twist-vane spacer grid can effectively improve the forced convection heat transfer in the dual-cooled annular fuel assembly with narrow gaps.
Keywords
Rod Bundle Flow; Dual-cooled Annular Fuel; Twist-vane Spacer Grid; Convection Heat Transfer;
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Times Cited By KSCI : 2  (Citation Analysis)
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1 Chun, T. H., Shin, C. H., In, W. K., Lee, K. H., Park, S. Y., Kim, H. T., Bae, K. H. and Song, K.W., 2009, "A Potential of Dual-cooled Annular Fuel for OPR-1000 Power Uprate," Proceedings of 2009 LWR Fuel Performance, Paris, France, Paper 2185.
2 In, W. K., Shin, C. H., Oh, D. S. and Chun, T. H., 2010, "Thermal-hydraulic and Thermomechanical Assessment of Dual-cooled Annular Fuel for the OPR-1000 Application," Proceedings of 2010 LWR Fuel Performance, Orlando, FL, USA, Paper 031.
3 Lee, C. Y., Shin, C. H., Park, J. Y. and In, W. K., 2012, "Experimental Study on Pressure Loss of Flow Parallel to Rod Bundle with Spacer Grid," Transactions of the Korean Society of Mechanical Engineers B, Vol. 36, No. 7, pp. 689-695.   DOI
4 Shen, Y. F., Cao, Z. D. and Liu, Q. G., 1991, "An Investigation of Crossflow Mixing Effect Caused by Grid Spacer with Mixing Blades in a Rod Bundle," Nuclear Engineering and Design, Vol. 125, pp. 111-119.   DOI
5 Yang, S. K. and Chung, M. K., 1996, "Spacer Grid Effects on Turbulent Flow in Rod Bundles," Journal of the Korean Nuclear Society, Vol. 28, pp. 56-71.
6 McClusky, H. L., Holloway, M. V., Beasley, D. E. and Conner, M. E., 2002, "Development of Swirling Flow in a Rod Bundle Subchannel," Journal of Fluids Engineering, Vol. 124, pp. 747-755.   DOI
7 McClusky, H. L., Holloway, M. V., Conover, T. A., Beasley, D. E., Conner M. E. and Smith, L. D., 2003, "Mapping of the Lateral Flow Field in Typical Subchannels of a Support Grid with Vanes," Journal of Fluids Engineering, Vol. 125, pp. 987-996.   DOI
8 Holloway, M. V., McClusky, H. L., Beasley, D. E. and Conner, M. E., 2004, "The Effect of Support Grid Features on Local, Single-phase Heat Transfer Measurements in Rod Bundles," Journal of Heat Transfer, Vol. 126, pp. 43-53.   DOI
9 Conner, M. E., Smith III, L. D., Holloway, M. V. and Beasley, D. E., 2005, "Heat Transfer Coefficient Testing in Nuclear Fuel Bundles with Mixing Vane Grids," 2005 Water Fuel Performance Mtg., Kyoto, Japan.
10 Holloway, M. V., Conover, T. A., McClusky, H. L., Beasley, D. E. and Conner, M. E., 2005, "The Effect of Support Grid Design on Azimuthal Variation in Heat Transfer Coefficient for Rod Bundles," Journal of Heat Transfer, Vol. 127, pp. 598-605.   DOI
11 In, W. K., Kang, H. S., Yoon, K. H., Jung, Y. H., Kim, H. H., Oh, D. S., Chun, T. H. and Song, K. N. (KAERI), 2008, "Twisted Deflector for Enhancing Coolant Mixing in a Nuclear Fuel Assembly," EP 1139348.
12 In, W. K., Oh, D. S., Lee, C. Y., Kwak, Y. K., Shin, C. H., Chun, T. H., Park, J. Y., Hwang, D. H., Kwon, H. and Kim, S. J., 2015, "Nuclear Fuel Thermal-Hydraulic Technology Development," KAERI/RR-3922/2014.
13 In, W. K., Shin, C. H. and Lee, C. Y., 2014, "Experimental Observation of Forced Flow Mixing in Tight-lattice Rod Bundle," Trans. ANS, Reno, Nevada, USA, 662-664.
14 In, W. K., Shin, C. H. and Lee, C. Y., 2015, "Convective Heat Transfer Experiment of Rod Bundle Flow with Twist-vane Spacer Grid," Nuclear Engineering and Design, Vol. 295, pp. 173-181.   DOI
15 Lee, C. Y., 2016, "Evaluation of Convective Heat Transfer Performance of Twist-Vane Spacer Grid in Rod Bundle Flow," Transactions of the Korean Society of Mechanical Engineers B, Vol. 40, No. 3, pp. 157-164.   DOI
16 Yao, S. C., Hochreiter, L. E. and Leech, W. J., 1982, "Heat-transfer Augmentation in Rod Bundles Near Grid Spacers," Journal of Heat Transfer, Vol. 104, pp. 76-81.   DOI
17 Miller, D. J., Cheung, F. B. and Bajorek, S. M., 2013, "On the Development of a Grid-enhanced Single-phase Convective Heat Transfer Correlation," Nuclear Engineering and Design, Vol. 264, pp. 56-60.   DOI
18 Lee, C. Y., Shin, C. H., Park, J. Y. and In, W. K., 2013, "An Experimental Investigation on Turbulent Flow Mixing in a Simulated $3{\times}3$ Dual-cooled Annular Fuel Bundle Using Particle Image Velocimetry," Nuclear Engineering and Design, Vol. 260, pp. 134-144.   DOI
19 Kline, S. J., 1985, "The Purposes of Uncertainty Analysis," Journal of Fluids Engineering, Vol. 107, pp. 153-160.   DOI