0
Research Papers

Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure

[+] Author and Article Information
Andrea Pucciarelli

Dipartimento di Ingegneria Civile e Industriale,
Università di Pisa,
Largo Lucio Lazzarino 2, Pisa 56126, Italy
e-mail: andrea.pucciarelli@yahoo.it

Walter Ambrosini

Dipartimento di Ingegneria Civile e Industriale,
Università di Pisa,
Largo Lucio Lazzarino 2, Pisa 56126, Italy
e-mail: walter.ambrosini@ing.unipi.it

1Corresponding author.

Manuscript received May 20, 2015; final manuscript received July 29, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011011 (Dec 09, 2015) (9 pages) Paper No: NERS-15-1090; doi: 10.1115/1.4031201 History: Received May 20, 2015; Accepted August 06, 2015

The paper further explores the application of computational fluid dynamics (CFD) codes for the study of the heat-transfer phenomena involved when working with fluids at supercritical pressure; bundle analysis is considered here in particular. As for previous simulations performed by the authors considering heat-transfer deterioration inside heated tubes, this application points out the limited capabilities of the most commonly used Reynolds-averaged Navier–Stokes models when approaching the heat-transfer deterioration phenomenon. It must be noted that some of the considered experimental conditions, which are very close to the pseudocritical temperature, represent at the same time one of the most challenging situations for the CFD codes and a very common situation if supercritical water-cooled reactors (SCWRs) will be developed. Improvements of the currently available turbulence models are then needed. The paper analyzes the most likely causes of the observed insufficient quality of the obtained predictions. In addition to comparing the measured and calculated wall temperature trends, the effect of the presence of the spacer grids on the turbulent flow is considered. Spacers are in fact very important to assure the structural stability of fuel, though they also affect the flow, generally improving the turbulence conditions in their neighborhood and slightly impairing it in the downstream region. A comparison between predictions performed including or not including the spacers is also performed.

Copyright © 2015 by ASME
Your Session has timed out. Please sign back in to continue.

References

Jackson, J. D., and Hall, W. B., 1979, “Forced Convection Heat Transfer to Fluids at Supercritical Pressure,” Turbulence Forced Convection in Channels and Bundles, Hemisphere Publishing Corporation, Manchester, pp. 563–611.
Jackson, J. D., and Hall, W. B., 1979, “Influences of Buoyancy on Heat Transfer to Fluids Flowing in Vertical Tubes Under Turbulent Conditions,” Turbulence Forced Convection in Channel and Bundles, Hemisphere Publishing Corporation, Manchester, pp. 613–640.
Jackson, J. D., 2009, “The Supercritical Pressure Water Heat Transfer Study at Manchester With Natural Circulation Test Facility,” IAEA Coordinated Research Programme (CRP), University of Manchester, Documentation delivered in the frame of the CRP of IAEA Heat Transfer Behaviour and Thermohydraulics Code Testing for Supercritical Water Cooled Reactors (SCWRs).
Watts, M. J., 1980, “Heat Transfer to Supercritical Pressure Water—Mixed Convection With Upflow and Downflow in a Vertical Tube,” Ph.D. thesis, University of Manchester.
Pioro, R. B., and Duffey, I. L., 2007, Heat Transfer and Hydraulic Resistance at Supercritical Pressure in Power-Engineering Applications, ASME Press, New York.
Pis’mennyy, E. N., Razumovskiy, V. G., and Maevskiy, E. M., 2005, “Experimental Study on Temperature Regimes to Supercritical Water Flowing in Vertical Tubes at Low Mass Fluxes,” Proceedings of the International Conference GLOBAL-2005 “Nuclear Energy System for Future Generation and Global Sustainability,” Tsukuba, Japan, Atomic Energy Society of Japan (AESJ), Japan.
Kim, D. E., and Kim, M. H., 2011, “Experimental Investigation of Heat Transfer in Vertical Upward and Downward Supercritical CO2 Flow in a Circular Tube,” Int. J. Heat Fluid Flow, 32(1), pp. 176–191. 0142-727X 10.1016/j.ijheatfluidflow.2010.09.001
Sharabi, M., Ambrosini, W., Forgione, N., and He, S., 2007, “Prediction of Experimental Data on Heat to Supercritical Water With Two-Equation Turbulence Models,” 3rd International Symposium on SCWR-Design and Technology, Shangai, China, Mar. 12–15.
Sharabi, M., 2008, “CFD Analyses of Heat Transfer and Flow Instability Phenomena Relevant to Fuel Bundles in Supercritical Water Reactors,” Ph.D. thesis, Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Università di Pisa, Pisa.
Badiali, S., 2011, “Numerical Investigation Using CFD Codes of Heat Transfer With Fluids at Supercritical Pressure,” B.Sc. thesis, Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Università di Pisa, Pisa, Italy.
De Rosa, M., 2010, “Computational Fluid-Dynamic Analysis of Experimental Data on Heat Transfer Deterioration With Supercritical Water,” M.Sc. thesis, Department of Mechanical Engineering and Nuclear, University of Pisa, Italy.
Pucciarelli, A., Borroni, I., Sharabi, M., and Ambrosini, W., 2015, “Results of 4-Equation Turbulence Models in the Prediction of Heat Transfer to Supercritical Pressure Fluids,” Nucl. Eng. Des., 481, pp. 5–14. 10.1016/j.nucengdes.2014.11.004
Zhao, M., Li, H., Yang, J., Gu, H., and Cheng, X., 2013, “Experimental Study on Heat Transfer to Supercritical Water Flowing through Circle Tubes and 2 x 2 Rod Bundles,” The 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6), Shenzhen, Guangdong, China, Mar. 3–7.
Misawa, T., Nakatsuka, T., Yoshida, H., Takase, K., Ezato, K., Seki, Y., Dairaku, M., Suzuki, S., and Enoeda, M., 2009, “Heat Transfer Experiments and Numerical Analysis of Supercritical Pressure Water in Seven-Rod Test Bundle,” Proceedings of the 13th InternationalTopical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-13), Kanazawa, Japan.
Rhode, M., Peeters, J. W. R., Pucciarelli, A., Kiss, A., Rao, Y., Onder, E. N., Mühlbauer, P., Batta, A., Hartig, M., Chatoorgoon, V., Thiele, R., Chang, D., Tavoularis, S., Novog, D., McClure, D., Gradecka, M., and Takase, K., 2015, “A Blind, Numerical Benchmark Study on Supercritical Water Heat Transfer Experiments in a 7-Rod Bundle,” The 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7), Helsinki, Finland, Mar. 15–18, VTT Technical Research Centre of Finland Ltd, Finland.
Documentation distributed by the Benchmark proposing organisation in March 2013, Japan Atomic Energy Agency.
CD-adapco, 2012, User Guide STAR-CCM+ Version 7.04.006.
Sharabi, M. B., and Ambrosini, W., 2009, “Discussion of Heat Transfer Phenomena in Fluids at Supercritical Pressure With the Aid of CFD Models,” Ann. Nucl. Energy, 36(1), pp. 60–71. 0306-4549 10.1016/j.anucene.2008.10.006
Abe, K., Kondoh, T., and Nagano, Y., 1994, “A New Turbulence Model for Predicting Fluid Flow and Heat Transfer in Separating and Reattaching Flows 1. Flow Field Calculations,” Int. J. Heat Mass Transfer, 37(1), pp. 139–151. 0017-9310 10.1016/0017-9310(94)90168-6
Menter, F. R., 1994, “Two-Equation Eddy-Viscosity Turbulence Modelling for Engineering Applications,” AIAA J., 32(8), pp. 1598–1605. 0001-1452 10.2514/3.12149

Figures

Grahic Jump Location
Fig. 3

Geometry of the problem and particular of the spacers shape, documentation provided by the authors of Ref. [13]

Grahic Jump Location
Fig. 2

Spacer geometry, taken from the documentation provided by the benchmark-proposing organization [16]

Grahic Jump Location
Fig. 1

Proposed geometry and considered computational domain, taken from the documentation provided by the benchmark-proposing organization [16]

Grahic Jump Location
Fig. 4

Comparison of the calculated wall temperature values with the experimental data

Grahic Jump Location
Fig. 5

Comparison of the calculated ranges with the experimental data

Grahic Jump Location
Fig. 6

Comparison of the calculated values with the experimental data when adopting the AKN (1994) model for Case 1

Grahic Jump Location
Fig. 7

Comparison of the calculated values with the experimental data when adopting the SST κ–ω (1994) model for Case 1

Grahic Jump Location
Fig. 8

Comparison of the calculated values with the experimental data when adopting the AKN (1994) model for Case 2

Grahic Jump Location
Fig. 9

Comparison of the calculated values with the experimental data when adopting the SST κ–ω (1994) model for Case 2

Grahic Jump Location
Fig. 10

Calculated wall temperature trend for Case B1 when considering the spacer grids and adopting the SST κ–ω (1994) model

Grahic Jump Location
Fig. 11

Calculated wall temperature trend for Case B1 when not considering the spacer grids and adopting the SST κ–ω (1994) model

Grahic Jump Location
Fig. 12

Considered section for the analyses of the spacer effect

Grahic Jump Location
Fig. 13

Calculated axial velocity distribution for Case B1 adopting the SST κ–ω (1994) model in the region straddling the spacer at 300 mm

Grahic Jump Location
Fig. 14

Calculated production term of turbulent kinetic energy for Case B1 adopting the SST κ–ω (1994) model in the region straddling the spacer at 300 mm

Grahic Jump Location
Fig. 18

(a) Calculated wall temperature trend for the regions in the vicinity of the thermocouples highlighted in the corresponding sketch. (b) Calculated wall temperature trend for the regions in the vicinity of the thermocouples highlighted in the corresponding sketch

Grahic Jump Location
Fig. 15

Calculated distribution of turbulent kinetic energy for Case B1 adopting the SST κ–ω (1994) model in the region straddling the spacer at 300 mm

Grahic Jump Location
Fig. 16

Calculated wall temperature trend for Case 1 when considering the spacer grids and adopting the AKN (1994) model

Grahic Jump Location
Fig. 17

Calculated wall temperature trend for Case 1 when not considering the spacer grids and adopting the AKN (1994) model

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In