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Assessment of fuel-rod meltdown in a severe accident at Bushehr nuclear power plant (BNPP)

  • M. Barzegari
  • M. AghaieEmail author
  • A. Zolfaghari
Article
  • 7 Downloads

Abstract

After the Fukushima disaster, interest in the evaluation of severe accidents in nuclear power plants and off-site consequences has significantly increased. Because experimental studies are difficult to conduct, computational methods play a substantial role in accident analysis. In this study, a severe accident in the Bushehr pressurized water reactor power plant caused by a station blackout with a total loss of alternating current power supply has been evaluated. This analysis presents the in-core damage of fuel rods and the release of fission products as well as the thermal hydraulic response of the station components during the loss of active emergency cooling systems. In this manner, a perfect model of the Bushehr nuclear power plant using the MELCOR code is prepared. The accident progression is simulated, and the thermal responses of the fuels and hydraulic components are presented. It is shown that, without operator intervention, steam generators will become dry in approximately 3000 s, and the heat sink of the reactor will be lost. The simulation results show that at approximately 8600 s, the upper parts of the core start melting. This model calculates the shortest available time for accident prevention and proves that the time available is sufficient for operator manual action to prevent a nuclear disaster.

Keywords

MELCOR Bushehr power plant Severe accident analysis WWER1000 Pressurized water reactor 

References

  1. 1.
    G.H. Su, S.P. Niu, Y.P. Zhang et al., The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR. Ann. Nucl. Energy 99, 9–18 (2016).  https://doi.org/10.1016/j.anucene.2016.09.008 CrossRefGoogle Scholar
  2. 2.
    J. Hasslberger, L. Boeck, L. Sattelmayer, Numerical simulation of deflagration-to-detonation transition in large confined volumes. J. Loss Prev. Process 36, 371–379 (2015).  https://doi.org/10.1016/j.jlp.2014.11.018 CrossRefGoogle Scholar
  3. 3.
    A. Chen, F.C. Moreira, J. Su, Thermal analysis of the melting process in a nuclear fuel rod. Appl. Therm. Eng. 68, 133–143 (2014).  https://doi.org/10.1016/j.applthermaleng.2014.04.005 CrossRefGoogle Scholar
  4. 4.
    D. Kancev, G. Zerovnik, M. Cepin, Uncertainty analysis in the nuclear industry: analytical unavailability modelling incorporating ageing of safety components. J. Loss Prev. Process 25, 643–649 (2012).  https://doi.org/10.1016/j.jlp.2012.01.009 CrossRefGoogle Scholar
  5. 5.
    V. Hassija, C.S. Kumar, K. Velusamy, Probabilistic safety assessment of multi-unit nuclear power plant sites—an integrated approach. J. Loss Prev. Process 32, 52–62 (2014).  https://doi.org/10.1016/j.jlp.2014.07.013 CrossRefGoogle Scholar
  6. 6.
    A. Chen, J. Su, Lumped parameter model for one-dimensional melting in a slab with volumetric heat generation. Appl. Therm. Eng. 60, 387–396 (2013).  https://doi.org/10.1016/j.applthermaleng.2013.07.018 CrossRefGoogle Scholar
  7. 7.
    Nuclear Energy Organization of IRAN (AEOI), Final Safety Analysis Report (FSAR) Chapters (4-5-15). Bushehr NPP, Unit 1 (2007)Google Scholar
  8. 8.
    T. Sevon, A MELCOR model of Fukushima Daiichi Unit 1 accident. Ann. Nucl. Energy 85, 1–11 (2015)CrossRefGoogle Scholar
  9. 9.
    Y. Onishi, Fukushima and Chernobyl nuclear accidents’ environmental assessments and U.S. Hanford Site’s waste management. Proc. IUTAM 10, 372–381 (2014).  https://doi.org/10.1016/j.piutam.2014.01.032 CrossRefGoogle Scholar
  10. 10.
    T. Haste, J. Birchley, E. Cazzoli et al., MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences. Nucl. Eng. Des. 236, 1099–1112 (2005).  https://doi.org/10.1016/j.nucengdes.2005.11.012 CrossRefGoogle Scholar
  11. 11.
    S. Park, J. Lee, A comparative study of station blackout scenario dynamics initiated by internal and seismic event in boiling water reactor. Ann. Nucl. Energy 108, 329–342 (2017).  https://doi.org/10.1016/j.anucene.2017.05.012 CrossRefGoogle Scholar
  12. 12.
    H. Lin, J. Wang, K. Haung et al., Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE. Ann. Nucl. Energy 89, 1–18 (2016).  https://doi.org/10.1016/j.anucene.2015.11.015 CrossRefGoogle Scholar
  13. 13.
    F. Zhou, D. Novog, RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators. Nucl. Eng. Des. 318, 35–53 (2017).  https://doi.org/10.1016/j.nucengdes.2017.04.014 CrossRefGoogle Scholar
  14. 14.
    A. Ghione, B. Noel, P. Vinal et al., Uncertainty and sensitivity analysis for the simulation of a station blackout scenario in the Jules Horowitz Reactor. Ann. Nucl. Energy 104, 28–41 (2017).  https://doi.org/10.1016/j.anucene.2017.02.008 CrossRefGoogle Scholar
  15. 15.
    L. Li, M. Wang, W. Tian et al., Severe accident analysis for a typical PWR using the MELCOR code. Prog. Nucl. Energy 71, 30–38 (2014).  https://doi.org/10.1016/j.pnucene.2013.10.014 CrossRefGoogle Scholar
  16. 16.
    J. Wang, Y. Zhang, K. Mao et al., MELCOR simulation of core thermal response during a station blackout initiated severe accident in China pressurized reactor (CPR1000). Prog. Nucl. Energy 81, 6–15 (2015).  https://doi.org/10.1016/j.pnucene.2014.12.008 CrossRefGoogle Scholar
  17. 17.
    L.M. Jiji, S. Gaye, Analysis of solidification and melting of PCM with energy generation. Appl. Therm. Eng. 26, 568–575 (2006).  https://doi.org/10.1016/j.applthermaleng.2005.07.008 CrossRefGoogle Scholar
  18. 18.
    Sandia National Laboratories, MELCOR Computer Code Manuals vol. 1: Primer and Users’ Guide-Version 1.8.6. NUREG/CR-6119, SAND 5713-2005Google Scholar
  19. 19.
    A. Bonelli, O. Mazzantini, M. Sonnenkalb et al., Station blackout analysis with MELCOR 1.8.6 code for Atucha 2 nuclear power plant. Sci. Technol. Nucl. Install. 62, 118–135 (2012).  https://doi.org/10.1155/2012/620298 CrossRefGoogle Scholar
  20. 20.
    S. Qiu, J. Wang, Y. Zhan et al., MELCOR simulation of core thermal response during a station Blackout initiated severe accident in China pressurized reactor (CPR1000). Prog. Nucl. Energy 81, 6–15 (2014).  https://doi.org/10.1016/j.pnucene.2014.12.008 CrossRefGoogle Scholar
  21. 21.
    M. Pavlova, P. Grudev, V. Hadjiev, Development and Validation of VVER-1000 Input Deck for Severe Accident Calculations with MELCOR Computer Code (International School on Nuclear Physics, Neutron Physics and Nuclear Energy, 2003), pp. 1–13Google Scholar
  22. 22.
    Sandia National Laboratories, MELCOR Computer Code Manuals vol. 2: Reference Manuals-Version 1.8.6. NUREG/CR-6119, SAND 5713-2005Google Scholar

Copyright information

© China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  1. 1.Engineering DepartmentShahid Beheshti University, G.C.TehranIran

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