Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Development of the vapor film thickness correlation in porous corrosion deposits on the cladding in PWR

  • Yuan Shen (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Zhengang Duan (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China) ;
  • Chuan Lu (Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China) ;
  • Li Ji (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Caishan Jiao (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Hongguo Hou (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Nan Chao (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Meng Zhang (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Yu Zhou (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University) ;
  • Yang Gao (Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University)
  • Received : 2022.03.28
  • Accepted : 2022.08.14
  • Published : 2022.12.25
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Abstract

The porous corrosion deposits (known as CRUD) adhered to the cladding have an important effect on the heat transfer from fuel rods to coolant in PWRs. The vapor film is the main constituent in the two-phase film boiling model. This paper presents a vapor film thickness correlation, associated with CRUD porosity, CRUD chimney density, CRUD particle size, CRUD thickness and heat flux. The dependences of the vapor film thickness on the various influential factors can be intuitively reflected from this vapor film thickness correlation. The temperature, pressure, and boric acid concentration distributions in CRUD can be well predicted using the two-phase film boiling model coupled with the vapor film thickness correlation. It suggests that the vapor thickness correlation can estimate the vapor film thickness more conveniently than the previously reported vapor thickness calculation methods.

Keywords

Acknowledgement

This work was financially supported by Sichuan Science and Technology Program (2021YJ0512).

References

  1. F. Carrette, M. Lafont, G. Chatainier, et al., Analysis and TEM examination of corrosion scales grown on Alloy 690 exposed to pressurized water at 325 ℃, Surf. Interface Anal. 34 (1) (2002) 135-138.  https://doi.org/10.1002/sia.1269
  2. W.A. Byers, J. Deshon, Structure and chemistry of PWR crud, in: International Conference Water Chemistry in Nuclear Reactors Systems Conference, San Francisco USA, 2004, pp. 11-14. 
  3. P. Athe, C. Jones, N. Dinh, Assessment of the predictive capability of VERA-CS for CASL challenge problems, Journal of Verification, Validation and Uncertainty Quantification 6 (2) (2021). 
  4. N. Cinosi, I. Haq, M. Bluck, et al., The effective thermal conductivity of crud and heat transfer from crud-coated PWR fuel, Nucl. Eng. Des. 241 (3) (2011) 792-798.  https://doi.org/10.1016/j.nucengdes.2010.12.015
  5. P. Cohen, Heat and mass transfer for boiling in porous deposits with chimneys 70 (138) (1974) 71-80. 
  6. C. Pan, B.G. Jones, A.J. Machiels, Concentration levels of solutes in porous deposits with chimneys under wick boiling conditions, Nucl. Eng. Des. 99 (1985) 317-327. 
  7. J. Henshaw, J.C. Mcgurk, H.E. Sims, et al., A model of chemistry and thermal hydraulics in PWR fuel crud deposits, J. Nucl. Mater. 353 (1-2) (2006) 1-11.  https://doi.org/10.1016/j.jnucmat.2005.01.028
  8. I.U. Haq, Heat and Mass Transfer Analysis for Crud Coated PWR Fuel, Imperial College London, 2011. 
  9. M. Short, D. Hussey, B. Kendrick, et al., Multiphysics modeling of porous CRUD deposits in nuclear reactors, J. Nucl. Mater. 443 (1-3) (2013) 579-587.  https://doi.org/10.1016/j.jnucmat.2013.08.014
  10. B.G. Park, S. Seo, S.J. Kim, et al., Meso-scale multi-physics full coupling within porous CRUD deposits on nuclear fuel, J. Nucl. Mater. 512 (2018) 100-117.  https://doi.org/10.1016/j.jnucmat.2018.10.002
  11. G. Wang, Improved Crud Heat Transfer Model for Dryout on Fuel Pin Surfaces at Pwr Operating Conditions, The Pennsylvania State University, 2009. 
  12. M. Jin, M. Short, Multiphysics modeling of two-phase film boiling within porous corrosion deposits, J. Comput. Phys. 316 (2016) 504-518.  https://doi.org/10.1016/j.jcp.2016.03.013
  13. J. Collier, J. Thome, Convective Boiling and Condensation, third ed., Oxford University Press, 1994. 
  14. D.Y. Yeo, H.C. No, Modeling heat transfer through corrosion product deposits on fuel rods in pressurized water reactors, Nucl. Eng. Des. 342 (2019) 308-319.  https://doi.org/10.1016/j.nucengdes.2018.12.008
  15. S. Dickinson, J. Henshaw, J.C. McGurk, et al., Modeling PWR Fuel Corrosion Product Deposition and Growth Processes, EPRI, Palo Alto, CA, 2004, p. 1009734. 
  16. J. Deshon, PWR Axial Offset Anomaly (AOA) Guidelines, Revision 1, EPRI, Palo Alto, CA, 2004, 1008102. 
  17. Ying Shi, Jinsheng Xiao, Shuhai Quan, Mu Pan, Runzhang Yuan, Fractal model for prediction of effective thermal conductivity of gas diffusion layer in proton exchange membrane fuel cell, J. Power Sources 185 (1) (2008) 241-247.  https://doi.org/10.1016/j.jpowsour.2008.07.010
  18. D.Y. Yeo, H.C. No, Modeling film boiling within chimney-structured porous media and heat pipes, Int. J. Heat Mass Tran. 124 (2018) 576-585.  https://doi.org/10.1016/j.ijheatmasstransfer.2018.03.093
  19. W. Woodside, J.H. Messmer, Thermal conductivity of porous media. II. Consolidated rocks, J. Appl. Phys. 32 (9) (1961) 1699. 
  20. P.J. Gierszewski, B.B. Mikic, N.E. Todreas, Property Correlations for Lithium, Sodium, Helium, Flibe and Water in Fusion Reactor Applications, Massachusetts Institute of Technology, Plasma Fusion Center, 1980. 
  21. J. Deshon, Simulated Fuel Crud Thermal Conductivity Measurements under Pressurized Water Reactor Conditions, EPRI, 2011. Technical Report 1022896. 
  22. J.L. Uhle, Boiling Heat Transfer Characteristics of Steam Generator U-Tube Fouling, Massachusetts Institute of Technology, 1997. 
  23. R. Salko Jr., T.L. Lange, E. Tatli, et al., Development of a Crud Induced Localized Corrosion Analysis Capability in VERA, Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2020.