DOI QR코드

DOI QR Code

CFD investigation of a JAEA 7-pin fuel assembly experiment with local blockage for SFR

  • Jeong, Jae-Ho (Department of Mechanical Engineering, Gachon University) ;
  • Song, Min-Seop (Department of Nuclear Engineering, Seoul National University)
  • Received : 2020.09.10
  • Accepted : 2021.05.09
  • Published : 2021.10.25

Abstract

Three-dimensional structures of a vortical flow field and heat transfer characteristics in a partially blocked 7-pin fuel assembly mock-up of sodium-cooled fast reactor have been investigated through a numerical analysis using a commercial computational fluid dynamics code, ANSYS CFX. The simulation with the SST turbulence model agrees well with the experimental data of outlet and cladding wall temperatures. From the analysis on the limiting streamline at the wall, multi-scale vortexes developed in axial direction were found around the blockage. The vortex core has a high cladding wall temperature, and the attachment line has a low cladding wall temperature. The small-scale vortex structures significantly enhance the convective heat transfer because it increases the turbulent mixing and the turbulence kinetic energy. The large-scale vortex structures supply thermal energy near the heated cladding wall surface. It is expected that control of the vortex structures in the fuel assembly plays a significant role in the convective heat transfer enhancement. Furthermore, the blockage plate and grid spacer increase the pressure drop to about 36% compared to the bare case.

Keywords

Acknowledgement

The research paper is made possible through the encouragement and support from Dr. Hiroyuki Ohshima of JAEA. This study has been supported by National R&D Program through the National Research Foundation of Korea funded by the Ministry of Science, ICT & Future Planning (No.2020R1G1A1099560). This work was also supported by the Gachon University research fund of 2019 (GCU-2019-0797).

References

  1. J.T. Han, Blockages in LMFBR Fuel Assemblies: a Review of Experimental and Theoretical Studies. No. ORNL/TM-5839, Oak Ridge National Lab., TN (USA), 1977.
  2. Hae-Yong Jeong, et al., Modeling of flow blockage in a liquid metal-cooled reactor subassembly with a subchannel analysis code, Nuclear technology 149 (1) (2005) 71-87. https://doi.org/10.13182/nt05-a3580
  3. Xiang Chai, et al., Numerical investigation of flow blockage accident in SFR fuel assembly, Nucl. Eng. Des. 359 (2020) 110437. https://doi.org/10.1016/j.nucengdes.2019.110437
  4. Di Piazza Ivan, et al., A CFD analysis of flow blockage phenomena in ALFRED LFR demo fuel assembly, Nucl. Eng. Des. 276 (2014) 202-215. https://doi.org/10.1016/j.nucengdes.2014.05.033
  5. Y. Daigo, K. Haga, A. Ohtsubo, Y. Kikuchi, Local Temperature Rise Due to a 6-Channel Blockage in a 7-Pin Bundle, JAPFNR-202, 1975.
  6. Jae-Ho Jeong, Min-Seop Song, Kwi-Lim Lee, Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR, Nucl. Eng. Des. 320 (2017) 28-43. https://doi.org/10.1016/j.nucengdes.2017.05.019
  7. K. Haga, Y. Daigo, Y. Kikuchi, A. Otsubo, The Effects of Bowing Distortions on Heat Transfer in a Seven-Pin Bundle, ASME Winter Annual Meeting, New York, NY, 1974.
  8. J. Smagorinsky, General circulation experiments with the primitive equations. I. The basic experiment, Mon. Weather Rev. 91 (1963) 99-165. https://doi.org/10.1175/1520-0493(1963)091<0099:GCEWTP>2.3.CO;2
  9. D.C. Wilcox, Re-assessment of the scale-determining equation for advanced turbulence models, AIAA J. 26 (11) (1988) 1299-1310. https://doi.org/10.2514/3.10041
  10. F.R. Menter, Two-equation eddy-viscosity turbulence models for engineering applications, AIAA J. 32 (8) (1994) 1598-1605. https://doi.org/10.2514/3.12149
  11. Bran van Leer, Upwind and high-resolution methods for compressible flow, 16th AIAA Computational Fluid Dynamics Conference (2003).
  12. A.E. Perry, M.S. Chong, A description of eddying motions and flow patterns using critical-point concepts, Annu. Rev. Fluid Mech. 19 (1987) 125-155. https://doi.org/10.1146/annurev.fl.19.010187.001013
  13. Konstantin Mikityuk, Heat transfer to liquid metal: review of data and correlations for tube bundles, Nucl. Eng. Des. 239 (4) (2009) 680-687. https://doi.org/10.1016/j.nucengdes.2008.12.014
  14. H. Graeber, M. Rieger, O.E. Dwyer, Experimental Study of Heat Transfer to Liquid Metals Flowing In-Line through Tube Bundles, EURATOM, Ispra, Italy, 1973.
  15. V.M. Borishanskii, M.A. Gotovskii, E.V. Firsova, Heat transfer to liquid metals in longitudinally wetted bundles of rods, Sov. Atom. Energy 27 (6) (1969) 1347-1350. https://doi.org/10.1007/BF01118660
  16. V.I. Subbotin, et al., Heat transfer in elements of reactors with a liquid metal coolant, Proceedings of the 3rd International Conference on Peaceful Use of Nuclear Energy 8 (1965).