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Science and Technology of Nuclear Installations
Volume 2018, Article ID 5462895, 19 pages
https://doi.org/10.1155/2018/5462895
Research Article

Numerical Simulation of Decontamination of Airborne Fission Products during In-Vessel Release Phase by Containment Spray

Department of Nuclear Engineering, Faculty of Engineering, King Abdulaziz University (KAU), P.O. Box 80204, Jeddah 21589, Saudi Arabia

Correspondence should be addressed to Khurram Mehboob; moc.liamg@uebrhmarruhk

Received 26 October 2017; Revised 18 January 2018; Accepted 13 February 2018; Published 17 April 2018

Academic Editor: Alejandro Clausse

Copyright © 2018 Khurram Mehboob. 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. M. Dehjourian, M. Rahgoshay, R. Sayareh, G. Jahanfarnia, and A. S. Shirani, “Effect of Spray System on Fission Product Distribution in Containment During a Severe Accident in a Two-Loop Pressurized Water Reactor,” Nuclear Engineering and Technology, vol. 48, no. 4, pp. 975–981, 2016. View at Publisher · View at Google Scholar · View at Scopus
  2. J. Malet and X. Huang, “Influence of spray characteristics on local light gas mixing in nuclear containment reactor applications,” Computers & Fluids, vol. 107, pp. 11–24, 2015. View at Publisher · View at Google Scholar · View at Scopus
  3. J. Malet, Z. Parduba, S. Mimouni, and J. Travis, “Achievements of spray activities in nuclear reactor containments during the last decade,” Annals of Nuclear Energy, vol. 74, no. C, pp. 134–142, 2014. View at Publisher · View at Google Scholar · View at Scopus
  4. F. C. Rahim, M. Rahgoshay, and S. K. Mousavian, “A study of large break LOCA in the AP1000 reactor containment,” Progress in Nuclear Energy, vol. 54, no. 1, pp. 132–137, 2012. View at Publisher · View at Google Scholar · View at Scopus
  5. F. C. Iglesias, B. J. Lewis, P. J. Reid, and P. Elder, “Fission product release mechanisms during reactor accident conditions,” Journal of Nuclear Materials, vol. 270, no. 1, pp. 21–38, 1999. View at Publisher · View at Google Scholar · View at Scopus
  6. A. Tigeras, M. Bachet, H. Catalette, and E. Simoni, “PWR iodine speciation and behaviour under normal primary coolant conditions: An analysis of thermodynamic calculations, sensibility evaluations and NPP feedback,” Progress in Nuclear Energy, vol. 53, no. 5, pp. 504–515, 2011. View at Publisher · View at Google Scholar · View at Scopus
  7. K. Mehboob and C. Xinrong, “Source term evaluation of two loop PWR under hypothetical severe accidents,” Annals of Nuclear Energy, vol. 50, pp. 271–284, 2012. View at Publisher · View at Google Scholar · View at Scopus
  8. State of Art Report (SOAR), “On Containment Thermal-hydraulics and Hydrogen Distribution,” CSNI/R(99)-16, State of Art, 1999. View at Google Scholar
  9. J. Malet, “Presentation of the tests matrix for the TOSQAN facility Spray Programme,” IRSN technical report, DSU/SERAC/LPMAC/03-06, 2003. View at Google Scholar
  10. J. Malet, P. Lemaitre, E. Porcheron et al., Benchmarking of CFD and LP codes for spray systems in containment applications: spray tests at two different scales in the TOSQAN and MISTRA facilities, CFD4NRS, 2006.
  11. A. Filippov, S. Grigoryev, N. Drobyshevsky, A. Kiselev, A. Shyukin, and T. Yudina, “CMFD simulation of ERCOSAM PANDA spray tests PE1 and PE2,” Nuclear Engineering and Design, vol. 299, pp. 81–94, 2016. View at Publisher · View at Google Scholar · View at Scopus
  12. S. Mimouni, J.-S. Lamy, J. Lavieville, S. Guieu, and M. Martin, “Modelling of sprays in containment applications with A CMFD code,” Nuclear Engineering and Design, vol. 240, no. 9, pp. 2260–2270, 2010. View at Publisher · View at Google Scholar · View at Scopus
  13. A. del Corno, S. Morandi, F. Parozzi, L. Araneo, and F. Casella, “Experiments on aerosol removal by high-pressure water spray,” Nuclear Engineering and Design, vol. 311, pp. 28–34, 2017. View at Publisher · View at Google Scholar · View at Scopus
  14. E. Porcheron, P. Lemaitre, A. Nuboer, V. Rochas, and J. Vendel, “Experimental investigation in the TOSQAN facility of heat and mass transfers in a spray for containment application,” Nuclear Engineering and Design, vol. 237, no. 15-17, pp. 1862–1871, 2007. View at Publisher · View at Google Scholar · View at Scopus
  15. T. Haste, F. Payot, C. Manenc et al., “Phébus FPT3: Overview of main results concerning the behaviour of fission products and structural materials in the containment,” Nuclear Engineering and Design, vol. 261, pp. 333–345, 2013. View at Publisher · View at Google Scholar · View at Scopus
  16. L. E. Herranz and B. Clément, “In-containment source term: Key insights gained from a comparison between the PHEBUS-FP programme and the US-NRC NUREG-1465 revised source term,” Progress in Nuclear Energy, vol. 52, no. 5, pp. 481–486, 2010. View at Publisher · View at Google Scholar · View at Scopus
  17. N. Girault, L. Bosland, S. Dickinson et al., “LWR severe accident simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry,” Nuclear Engineering and Design, vol. 243, pp. 371–392, 2012. View at Publisher · View at Google Scholar · View at Scopus
  18. H. Anglart, F. Alavyoon, and R. Novarini, “Study of spray cooling of a pressure vessel head of a boiling water reactor,” Nuclear Engineering and Design, vol. 240, no. 2, pp. 252–257, 2010. View at Publisher · View at Google Scholar · View at Scopus
  19. M. Jain, B. John, K. N. Iyer, and S. V. Prabhu, “Characterization of the full cone pressure swirl spray nozzles for the nuclear reactor containment spray system,” Nuclear Engineering and Design, vol. 273, pp. 131–142, 2014. View at Publisher · View at Google Scholar · View at Scopus
  20. L. S. Lebel, M. H. Piro, R. Maccoy, A. Clouthier, and Y.-S. Chin, “Concept for a cyclonic spray scrubber as a fission product removal system for filtered containment venting,” Nuclear Engineering and Design, vol. 297, pp. 60–71, 2016. View at Publisher · View at Google Scholar · View at Scopus
  21. K. Mehboob and M. S. Aljohani, “Effect of Spray System on in Containment Fission Product Washout During In-Vessel Release Phase,” in Proceedings of the 2017 25th International Conference on Nuclear Engineering, p. V002T03A005, Shanghai, China. View at Publisher · View at Google Scholar
  22. N. Karl-Heinz, The Radiochemistry of Nuclear Power Plants with Light Water Reactors, Walter de Gruyter Berlin, New York, NY, USA, 1st edition, 1997.
  23. Lechler inc, “Spray Nozzles for Nuclear Power Generation,” 2017, http://www.lechler.de/is-bin/intershop.static/WFS/LechlerDE-Shop-Site/LechlerDE-Shop/en_IN/PDF/05_service_support/industrie/broschueren/englisch/lechler_brochure_nuclear_power_GB_0314.pdf.
  24. A. M. Bukrinsky, Y. V. Rzheznikov, Y. V. Shvyryaev et al., “Accident Localization System under LB LOCA conditions at NPP with VVER-440,” Applied Thermal Engineering, vol. 4, pp. 47–49, 1978. View at Google Scholar
  25. V. N. Blinkov, O. I. Melikhov, V. I. Melikhov, M. V. Davydov, H. Wolff, and S. Arndt, “Experimental Studies for the VVER-440/213 Bubble Condenser System for Kola NPP at the Integral Test Facility BC V-213,” Science and Technology of Nuclear Installations, vol. 2012, pp. 1–20, 2012. View at Publisher · View at Google Scholar
  26. D. Powers and S. Burson, “A simplified model of aerosol removal by containment sprays,” Tech. Rep. NUREG/CR-5966, 1993. View at Publisher · View at Google Scholar
  27. K. Mehboob, K. Park, and R. Khan, “Quantification of in-containment fission products source term for 1000 MWe PWR under loss of coolant accident,” Annals of Nuclear Energy, vol. 75, pp. 365–376, 2015. View at Publisher · View at Google Scholar · View at Scopus
  28. K. Jak, Nuclear power plant modeling and steam generator stability analysis [Ph.D. thesis], The University of Michigan, 1981.
  29. USNRC, “Reactor safety study. An assessment of accident risks in U. S. commercial nuclear power plants. Appendix XI. Analysis of comments on the draft WASH-1400 report. [PWR and BWR],” Tech. Rep. WASH-1400(App.11), 1975. View at Publisher · View at Google Scholar
  30. USNRC, Severe Accident Risks: An Assessment for Five U.S, Nuclear Power Plants. NUREG-1150. U.S. Nuclear Regulatory Commission, S, 1990.
  31. J. Knudsen, Properties of Air- Steam Mixtures Containing Small Amounts of Iodine. BNWL-1326, Battelle Memorial Institute Pacific Northwest Laboratories Richland, Washington, Wash, USA, 1970. View at Publisher · View at Google Scholar
  32. R. K. Hillard and L. F. Coleman, Fluid and energy system department, Physics and Engineering Division. AEC Research and development Report, BNWL-1457, Pacific North west Laboratories, 1970.
  33. L. Soffer et al., Accident Source Terms for Light-Water Nuclear Power Plants, NUREG-1465, U.S. Nuclear Regulatory Commission, 1995.
  34. USNRC, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, Regulatory Guide 1.183,” 2000.
  35. K. Mehboob, C. Xinrong, R. Ahmed, and M. Ali, “Numerical simulation of radioisotope's dependency on containment performance for large dry PWR containment under severe accidents,” Nuclear Engineering and Design, vol. 262, pp. 435–451, 2013. View at Publisher · View at Google Scholar · View at Scopus
  36. K. Mehboob and M. S. Aljohani, “Modeling and simulation of radio-iodine released inside the containment as result of an accident,” Progress in Nuclear Energy, vol. 88, pp. 75–87, 2016. View at Publisher · View at Google Scholar · View at Scopus
  37. L. Hu, Y. Zhang, L. Li, G. H. Su, W. Tian, and S. Qiu, “Investigation of severe accident scenario of PWR response to LOCA along with SBO,” Progress in Nuclear Energy, vol. 83, pp. 159–166, 2015. View at Publisher · View at Google Scholar · View at Scopus
  38. A. El-Jaby, B. J. Lewis, W. T. Thompson, F. Iglesias, and M. Ip, “A general model for predicting coolant activity behaviour for fuel-failure monitoring analysis,” Journal of Nuclear Materials, vol. 399, no. 1, pp. 87–100, 2010. View at Publisher · View at Google Scholar · View at Scopus
  39. NUREG/CR-009, Technological bases for models of spray washout of airborne contaminants in containment vessels, U.S Nuclear Regulatory Commission, 1978.
  40. A. G. Croft, “A Users Manual for the,” in ORIGEN2 Computer Code, Rep. ORNL/TM-7175, Oak Ridge National Laboratory, Oak Ridge, 1980. View at Google Scholar
  41. S. U. Kim and C. S. Kang, “Evaluation of Radioactive Source term in the System integrated Modular Advanced Reactor,” The Korean Society of Nuclear Medicine, vol. 31, no. 1, p. 16, 1999. View at Google Scholar
  42. Y. Zhao, L. Zhang, and J. Tong, “Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant,” Progress in Nuclear Energy, vol. 81, pp. 264–275, 2015. View at Publisher · View at Google Scholar · View at Scopus
  43. E. Porcheron, P. Lemaitre, D. Marchand, W. Plumecocq, A. Nuboer, and J. Vendel, “Experimental and numerical approaches of aerosol removal in spray conditions for containment application,” Nuclear Engineering and Design, vol. 240, no. 2, pp. 336–343, 2010. View at Publisher · View at Google Scholar · View at Scopus
  44. NUREG CR 0800, “Standard review plan for the review of safety analysis reports for nuclear power plants: LWR edition,” U.S. Nuclear Regulatory Commission, 1978. View at Google Scholar