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Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment

  • Gao, Pengcheng (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Zhang, Bin (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Li, Jishen (School of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Shan, Jianqiang (School of Nuclear Science and Technology, Xi'an Jiaotong University)
  • Received : 2020.12.30
  • Accepted : 2021.07.18
  • Published : 2022.01.25

Abstract

Cladding ballooning and rupture are the important phenomena at the early stage of a severe accident. Most severe accident analysis codes determine the cladding rupture based on simple parameter models. In this paper, a FRTMB module was developed using the thermal-mechanical model to analyze the fuel mechanical behavior. The purpose is to judge the cladding rupture with the severe accident analysis code. The FRTMB module was integrated into the self-developed severe accident analysis code ISAA to simulate the PHEBUS FPT3 experiment. The predicted rupture time and temperature of the cladding were basically consistent with the measured values, which verified the correctness and effectiveness of the FRTMB module. The results showed that the rising of gas pressure in the fuel rod and high temperature led to cladding ballooning. Consequently, the cladding hoop strain exceeded the strain limit, and the cladding burst. The developed FRTMB module can be applied not only to rod-type fuel, but also to plate-type fuel and other types of reactor fuel rods. Moreover, the FRTMB module can improve the channel blockage model of ISAA code and make contributions to analyzing the effect of clad ballooning on transient and subsequent parts of core degradation.

Keywords

Acknowledgement

This study is financially supported by Innovative Scientific Program of CNNC.

References

  1. P. Von der Hardt, A.V. Jones, C. Lecomte, A. Tattegrain, Nuclear Safety Research: the Phebus FP severe accident experimental program, Nucl. Saf. 35(2) (1994) 187-205.
  2. B. Clement, R. Zeyen, The objectives of the Phebus FP experimental programme and main findings, Ann. Nucl. Energy 61 (2013) 4-10, https://doi.org/10.1016/j.anucene.2013.03.037.
  3. Irsn, Nuclear Power Reactor Core Melt Accidents - Current State of Knowledge, EDP Sciences, 2015, ISBN 978-2-7598-1835-8.
  4. P. March, B. Simondi-Teisseire, Overview of the facility and experiments performed in Phebus FP, Ann. Nucl. Energy 61 (Nov) (2013) 11-22, https://doi.org/10.1016/j.anucene.2013.03.040.
  5. B.R. Sehgal, Nuclear safety in light water reactors severe accident phenomeneology, Academic Press Elsevier, 2012, https://doi.org/10.1016/C2010-0-67817-5.
  6. S. Suman, Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations, Nuclear Engineering and Technology (2021), https://doi.org/10.1016/j.net.2020.07.017.
  7. M.S. Veshchunov, V.E. Shestak, Model for melt blockage (slug) relocation and physico-chemical interactions during core degradation under severe accident conditions, Nucl. Eng. Des. 238 (1997) 3500-3507, https://doi.org/10.1016/j.nucengdes.2008.08.012, 12(2008).
  8. R.O. Gauntt, J.E. Cash, R.K. Cole, et al., MELCOR Computer Code Manuals 1-2, version 1.8.6, U.S. Nuclear Regulatory Commission, Sandia National Laboratories, 2005.
  9. MELCOR Computer Code Manuals Vol. 3: MELCOR Assessment Problems Version 2.1.7347, 2015.
  10. Xin Gong, Yijie Jiang, Shurong Ding, Yong zhong, et al., Simulation OF the IN-pile behaviors evolution IN nuclear fuel rods with the irradiation damage effects, Acta Mech. Solida Sin. 27 (2014) 567, https://doi.org/10.1016/S0894-9166(15)60001-5.
  11. Timo Ikonen, et al., Module for thermomechanical modeling of LWR fuel in multiphysics simulations, Ann. Nucl. Energy 84 (oct) (2015) 111-121, https://doi.org/10.1016/j.anucene.2014.11.004.
  12. U.S. Nuclear Regulatory Commission, Division of Systems Analysis. Fuel Rod Behavior and Uncertainty Analysis by FRAPTRAN/TRACE/Dakota Code in Maanshan LBLOCA. Washington, DC: Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2016.
  13. R.L. Williamson, et al., Multi-dimensional simulation of LWR fuel behavior in the BISON fuel performance code, J. Occup. Med. 68 (2016) 2930-2937, https://doi.org/10.1007/s11837-016-2115-7, 11.
  14. T. Glantz, et al., DRACCAR: a multi-physics code for computational analysis of multi-rod ballooning, cool ability and fuel relocation during LOCA transients. Part Two: overview of modeling capabilities for LOCA, Nucl. Eng. Des. 339 (2018) 202-214, https://doi.org/10.1016/j.nucengdes.2018.06.022.
  15. Janos Gado, Agnes Griger, Katalin Kulacsy, The fuel behaviour code FUROM and its high burn-up simulation capabilities, Nucl. Eng. Des. 327 (FEB) (2018) 274-285, https://doi.org/10.1016/j.nucengdes.2017.12.012.
  16. E. Syrjalahti, T. Ikonen, V. Tulkki, Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core, Ann. Nucl. Energy 125 (2019) 121-131, https://doi.org/10.1016/j.anucene.2018.10.039.
  17. A.G. Pastore, et al., Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: cladding modeling developments and simulation of separate-effects experiments, J. Nucl. Mater. 543 (2020), https://doi.org/10.1016/j.jnucmat.2020.152537.
  18. H. Kim, Sunguk Lee, Jinsu Kim, et al., Development of MERCURY for simulation of multidimensional fuel behavior for LOCA condition, Nucl. Eng. Des. 369 (2020) 110853, https://doi.org/10.1016/j.nucengdes.2020.110853.
  19. Pengcheng Gao, Bin Zhang, et al., Development of mechanistic cladding rupture model for integrated severe accident code ISAA. Part I: module verification and application in CAP1400, Ann. Nucl. Energy 158 (2021) 2-3, https://doi.org/10.1016/j.anucene.2021.108305, 108305.
  20. P.C. Gao, Bin Zhang, et al., DEVELOPMENT OF MECHANISTIC CLADDING RUPTURE MODEL FOR SEVERE ACCIDENT ANALYSIS AND APPLICATION, National Energy Nuclear Power Software Key Laboratory 2020 Academic Annual Meeting, 2020, pp. 499-506.
  21. K. Geelhood, W. Luscher, P. Raynaud, et al., FRAPCON-4.0: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup. Nuclear Regulatory Commission, Pacific Northwest Lab., Richland, WA (United States), 2015. Washington, DC (United States). Div. of Systems Technology.
  22. Kenneth Geelhood, Walter Luscher, Ian Porter, Material Property Correlations: Comparisons between FRAPCON-4.0, FRAPTRAN-2.0, and MATPRO, 2015, https://doi.org/10.2172/1030897.
  23. Kenneth Geelhood, Walter Luscher, J.M. Cuta, Ian Porter, FRAPTRAN-2.0: A Computer Code for the Transient Analysis of Oxide Fuel Rods, 2016.
  24. Institut de Protection et de Surete Nucleaire (Ipsn), Final Report FPT1, PHEBUSPF, IPSN/JRC, Saint Paul-lez-Durance Cedex, France, 2000.
  25. T. Ikeda, M. Terada, H. Karasawa, et al., Analysis of core degradation and fission products release in phebus FPT1 test at IRSN by detailed severe accidents analysis code, IMPACT/SAMPSON, J. Nucl. Sci. Technol. 40 (8) (2003) 591-603, https://doi.org/10.1080/18811248.2003.9715396.
  26. B. Clement, T. Haste, Thematic network for a phebus FPT-1 international standard problem, in: OECD/NEA Comparison Report on International Standard Problem ISP-46, 2003. PHEBUS FPT-1).
  27. B. Clement, T. Haste, E. Krausmann, et al., Thematic network for a Phebus FPT1 international standard problem (THENPHEBISP), Nucl. Eng. Des. 235 (2/4) (2005) 347-357. https://doi.org/10.1016/j.nucengdes.2004.08.057
  28. M. Leskovar, Simulation of the phebus FPT1 experiment with MELCOR 1.8.5, Int. Conf. Nucl. Energy New Eur. (2002) 1-8, 2002.
  29. Snl, MELCOR 2.1 Computer Code Manual - Volume 3 - Code Assessment, 2015, 2015.
  30. Jun Ho Bae, et al., Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code, Nucl. Eng. Des. 320 (2017) 258-268, https://doi.org/10.1016/j.nucengdes.2017.05.030.
  31. Snl, MELCOR 2.2 Computer Code Manual - Volume 1 - User Guide, 2017, 2017.
  32. L.L. Humphries. https://www.psi.ch/sites/default/files/import/emug/WS2018EN/WS_2018_03.pdf, 2018d.
  33. U.S. Nrc, Accident Source Terms for Light-Water Nuclear Power Plants, 1995. NUREG-1465.
  34. Snl, MELCOR Best Practices as Applied in the State-Of-The-Art Reactor Consequence Analyses (SOARCA) Project, U.S. NC Report NUREG/CR-7008, 2014, 2014.
  35. Mazzini, Guido, Severe accident phenomenology analyses and fission gas release in advanced nuclear reactors, Pisa University Press, 2012. http://etd.adm.unipi.it/theses/available/etd-04302012-144408/.
  36. Georges Repetto, et al., Preliminary analyses of the phebus FPT3 experiment using severe accident codes (ATHLET-CD, ICARE/CATHARE, MELCOR), Nucl. Technol. 176 (2011) 352-371, https://doi.org/10.13182/NT11-A13313, 3.
  37. T. Haste, F. Payot, P.D.W. Bottomley, Transport and deposition in the Phebus FP circuit, Ann. Nucl. Energy 61 (Nov) (2013) 102-121, https://doi.org/10.1016/j.anucene.2012.10.032.