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Science and Technology of Nuclear Installations
Volume 2019, Article ID 9537421, 8 pages
https://doi.org/10.1155/2019/9537421
Research Article

A Combined Method for Predicting the Boron Deposited Mass and the CIPS Risk

School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China

Correspondence should be addressed to Xiaojing Liu; nc.ude.utjs@uilgnijoaix

Received 26 December 2018; Accepted 12 February 2019; Published 26 March 2019

Academic Editor: Arkady Serikov

Copyright © 2019 Shengzhe Li et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

  1. J. Deshon, PWR Axial Offset Anomaly (AOA) Guidelines, Revision 1, EPRI, Palo Alto, Calif,USA, 2004.
  2. N. B. Hospeti and R. B. Mesler, “Deposits formed beneath bubbles during nucleate boiling of radioactive calcium sulfate solutions,” AIChE Journal, vol. 11, no. 4, pp. 662–665, 1965. View at Publisher · View at Google Scholar · View at Scopus
  3. E. P. Partridge and A. H. White, “Mechanism of formation of calcium sulfate boiler scale,” Industrial & Engineering Chemistry, vol. 21, no. 9, pp. 834–838, 1929. View at Publisher · View at Google Scholar
  4. R. V. Macbeth, “Boiling on surfaces overlayed with a porous deposit: heat transfer rates obtainable by capillary action,” Atomic Energy Establishment AEEW-R--711, Winfrith, England, 1971. View at Google Scholar
  5. P. Cohen, “Heat and mass transfer for boiling in porous deposits with chimneys,” in Proceedings of the in AICHE Symposium series 70, pp. 71–80, American Institute of Chemical Engineers, 1974.
  6. I. U. Haq, N. Cinosi, M. Bluck, G. Hewitt, and S. Walker, “Modelling heat transfer and dissolved species concentrations within PWR crud,” Nuclear Engineering and Design, vol. 241, no. 1, pp. 155–162, 2011. View at Publisher · View at Google Scholar · View at Scopus
  7. J. Henshaw, J. C. McGurk, H. E. Sims, A. Tuson, S. Dickinson, and J. Deshon, “A model of chemistry and thermal hydraulics in PWR fuel crud deposits,” Journal of Nuclear Materials, vol. 353, no. 1-2, pp. 1–11, 2006. View at Publisher · View at Google Scholar · View at Scopus
  8. M. Jin and M. Short, “Multiphysics modeling of two-phase film boiling within porous corrosion deposits,” Journal of Computational Physics, vol. 316, pp. 504–518, 2016. View at Publisher · View at Google Scholar · View at MathSciNet · View at Scopus
  9. C. Pan, B. G. Jones, and A. J. Machiels, “Concentration levels of solutes in porous deposits with chimneys under wick boiling conditions,” Nuclear Engineering and Design, vol. 99, no. C, pp. 317–327, 1987. View at Publisher · View at Google Scholar · View at Scopus
  10. C. Pan, B. G. Jones, and A. J. Machiels, “Wick boiling performance in porous deposits with chimneys,” in Proceedings of the ASME, National Heat Transfer Conference Symposium on Multiphase flow and Heat Transfer, 1985.
  11. M. P. Short, D. Hussey, B. K. Kendrick, T. M. Besmann, C. R. Stanek, and S. Yip, “Multiphysics modeling of porous CRUD deposits in nuclear reactors,” Journal of Nuclear Materials, vol. 443, no. 1-3, pp. 579–587, 2013. View at Publisher · View at Google Scholar · View at Scopus
  12. I. Dumnernchanvanit, V. K. Mishra, N. Q. Zhang et al., “The fractalline properties of experimentally simulated PWR fuel crud,” Journal of Nuclear Materials, vol. 499, pp. 294–300, 2018. View at Publisher · View at Google Scholar · View at Scopus
  13. B. M. Yu, “Analysis of flow in fractal porous media,” Applied Mechanics Reviews, vol. 61, no. 5, Article ID 050801, 2008. View at Publisher · View at Google Scholar
  14. V. Petrov, B. K. Kendrick, D. Walter, A. Manera, and J. Secker, “Prediction of CRUD deposition on PWR fuel using a state-of-the-art CFD-based multi-physics computational tool,” Nuclear Engineering and Design, vol. 299, pp. 95–104, 2016. View at Publisher · View at Google Scholar · View at Scopus
  15. S. Li and X. Liu, “Development of boron tracking and boron hideout (CRUD) model based on subchannel approach,” Nuclear Engineering and Design, vol. 338, pp. 166–175, 2018. View at Publisher · View at Google Scholar · View at Scopus
  16. R. Salko et al., “Development of COBRA-TF for modeling full-core, reactor operating cycles,” Advances in Nuclear Fuel Management V (ANFM 2015), 2015. View at Google Scholar
  17. D. J. Walter, B. K. Kendrick, V. Petrov, A. Manera, B. Collins, and T. Downar, “Proof-of-principle of high-fidelity coupled CRUD deposition and cycle depletion simulation,” Annals of Nuclear Energy, vol. 85, pp. 1152–1166, 2015. View at Publisher · View at Google Scholar · View at Scopus
  18. D. J. Walter and A. Manera, “CRUD, boron, and burnable absorber layer 2-D modeling requirements using MOC neutron transport,” Annals of Nuclear Energy, vol. 87, pp. 388–399, 2016. View at Publisher · View at Google Scholar · View at Scopus
  19. L. Zou, H. Zhang, J. Gehin, and B. Kochunas, “Coupled thermal-hydraulic/neutronics/crud framework in prediction of crud-induced power shift phenomenon,” Nuclear Technology, vol. 183, no. 3, pp. 535–542, 2013. View at Publisher · View at Google Scholar · View at Scopus
  20. Boron-Induced Offset Anomaly Risk Assessment Tool Version 3.0, EPRI, Palo Alto, Calif, USA, 2010.
  21. J. Deshon, D. Hussey, B. Kendrick, J. McGurk, J. Secker, and M. Short, “Pressurized water reactor fuel crud and corrosion modeling,” JOM: The Journal of The Minerals, Metals & Materials Society (TMS), vol. 63, no. 8, pp. 64–72, 2011. View at Publisher · View at Google Scholar · View at Scopus
  22. C. W. Stewart, “VIPRE-01: a thermal-hydraulic code for reactor cores,” Tech. Rep., Electric Power Research Institute, Pacific Northwest Laboratory, Palo Alto, Calif, USA, Richland, Washington, USA.
  23. G. Marleau, A. Hébert, and R. Roy, “A user guide for DRAGON 3.06,” Rep. IGE-174 Rev 7, vol. 7, 2008. View at Google Scholar
  24. V. G. Zimin, SKETCH-N: A Nodal Neutron Diffusion Code for Solving Steady-State and Kinetics Problems, JAERI Report, Tokyo, Japan, 2011.
  25. S. Levy, “Forced convection subcooled boiling-prediction of vapor volumetric fraction,” International Journal of Heat and Mass Transfer, vol. 10, no. 7, pp. 951–965, 1967. View at Publisher · View at Google Scholar · View at Scopus
  26. W. M. Rohsenow, J. P. Hartnett, and Y. I. Cho, Handbook of Heat Transfer, McGraw-Hill, New York, NY, USA, 1998.
  27. J. Buongiorno, “Can corrosion and CRUD actually improve safety margins in LWRs?” Annals of Nuclear Energy, vol. 63, pp. 9–21, 2014. View at Publisher · View at Google Scholar · View at Scopus
  28. S. Z. Li, X. J. Liu, and X. Cheng, “Development of Boron transport model based on subchannel approach,” in Proceedings of the 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, 9 October 2016.
  29. D. J. Walter, A High Fidelity Multiphysics Framework for Modeling CRUD Deposition on PWR Fuel Rods, University of Michigan, 2016.
  30. A. T. Godfrey, “VERA Core Physics Benchmark Progression Problem Specifications,” CASL-U-2012-0131-004, p. 189, 2014. View at Google Scholar
  31. A. T. Nelson, J. T. White, D. A. Andersson et al., “Thermal expansion, heat capacity, and thermal conductivity of nickel ferrite (NiFe2O4),” Journal of the American Ceramic Society, vol. 97, no. 5, pp. 1559–1565, 2014. View at Publisher · View at Google Scholar · View at Scopus
  32. L. S. Tong, “Prediction of departure from nucleate boiling for an axially non-uniform heat flux distribution,” Journal of Nuclear Energy, vol. 21, no. 3, pp. 241–248, 1967. View at Publisher · View at Google Scholar · View at Scopus