Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor

  • Received : 2015.06.08
  • Accepted : 2015.08.23
  • Published : 2016.02.25
Download PDF
⟨ Previous Next ⟩

Abstract

A steam explosion may occur during a severe accident, when the molten core comes into contact with water. The pressurized water reactor and boiling water reactor ex-vessel steam explosion study, which was carried out with the multicomponent three-dimensional Eulerian fuel-coolant interaction code under the conditions of the Organisation for Economic Co-operation and Development (OECD) Steam Explosion Resolution for Nuclear Applications project reactor exercise, is presented and discussed. In reactor calculations, the largest uncertainties in the prediction of the steam explosion strength are expected to be caused by the large uncertainties related to the jet breakup. To obtain some insight into these uncertainties, premixing simulations were performed with both available jet breakup models, i.e., the global and the local models. The simulations revealed that weaker explosions are predicted by the local model, compared to the global model, due to the predicted smaller melt droplet size, resulting in increased melt solidification and increased void buildup, both reducing the explosion strength. Despite the lower active melt mass predicted for the pressurized water reactor case, pressure loads at the cavity walls are typically higher than that for the boiling water reactor case. This is because of the significantly larger boiling water reactor cavity, where the explosion pressure wave originating from the premixture in the center of the cavity has already been significantly weakened on reaching the distant cavity wall.

Keywords

References

  1. M.L. Corradini, B.J. Kim, M.D. Oh, Vapor explosions in light water reactors, a review of theory and modelling, Prog. Nucl. Energy 22 (1988) 1-117. https://doi.org/10.1016/0149-1970(88)90004-2
  2. G. Berthoud, Vapour explosions, Annu. Rev. Fluid Mech. 32 (2000) 573-611. https://doi.org/10.1146/annurev.fluid.32.1.573
  3. T.G. Theofanous, The study of steam explosions in nuclear systems, Nucl. Eng. Des. 155 (1995) 1-26. https://doi.org/10.1016/0029-5493(94)00864-U
  4. H. Esmaili, M. Khatib-Rahbar, Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000, Nucl. Eng. Des. 235 (2005) 1583-1605. https://doi.org/10.1016/j.nucengdes.2005.02.003
  5. M. Leskovar, M. Ursic, Estimation of ex-vessel steam explosion pressure loads, Nucl. Eng. Des. 239 (2009) 2444-2458. https://doi.org/10.1016/j.nucengdes.2009.07.023
  6. M.L. Corradini, Vapor explosions: a review of experiments for accident analysis, Nucl. Saf. 32 (1991) 337-362.
  7. I. Huhtiniemi, D. Magallon, H. Hohmann, Results of Recent KROTOS FCI tests: aluminia versus corium melts, Nucl. Eng. Des. 189 (1999) 379-389. https://doi.org/10.1016/S0029-5493(98)00269-6
  8. S.W. Hong, P. Piluso, M. Leskovar, Status of the OECD-SERENA Project for the resolution of ex-vessel steam explosion risks, J. Energy Power Eng. 7 (2013) 423-431.
  9. M. Leskovar, S. Basu, C. Brayer, M. Buck, M. Burger, M. Corradini, R. Meignen, SERENA Analytical Working Group Outcome Document, OECD/NEA SERENA AWG/Sec/(14)1, 2014.
  10. R. Meignen, S. Picchi, J. Lamome, B. Raverdy, S.C. Escobar, G. Nicaise, The challenge of modeling fuel-coolant interaction: part I-premixing, Nucl. Eng. Des. 280 (2014) 511-527. https://doi.org/10.1016/j.nucengdes.2014.08.029
  11. R. Meignen, B. Raverdy, S. Picchi, J. Lamome, The challenge of modeling fuel-coolant interaction: part II-steam explosion, Nucl. Eng. Des. 280 (2014) 528-541. https://doi.org/10.1016/j.nucengdes.2014.08.028
  12. D. Magallon, I. Huhtiniemi, Corium melt quenching tests at low pressure and subcooled water in FARO, Nucl. Eng. Des. 204 (2001) 369-376. https://doi.org/10.1016/S0029-5493(00)00318-6
  13. R. Meignen, Analysis of FARO Premixing Calculations with MC3D in View of Reactor Applications for the PSA Level 2 V2, IRSN Report, DPEA/SEAC/03-026, 2004.
  14. D. Magallon, SERENA Programme Reactor Exercise, Synthesis of Calculations, Report, 2012.
  15. J.M. Seiler, B. Tourniaire, F. Defoort, K. Froment, Consequences of material effects on in-vessel retention, Nucl. Eng. Des. 237 (2007) 1752-1758. https://doi.org/10.1016/j.nucengdes.2007.03.007
  16. GEMINI2: Gibbs Energy MINImizer User Guide, THERMODATA-INPG-CNRS, France, 2003.
  17. NUCLEA-09, Thermodynamic Database, THERMODATA, 2009.

Cited by

  1. Assessment of steel components and reinforced concrete structures under steam explosion conditions vol.60, pp.2, 2016, https://doi.org/10.12989/sem.2016.60.2.337
  2. Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor vol.100, pp.None, 2016, https://doi.org/10.1016/j.pnucene.2017.06.019
  3. Structural Integrity Evaluation of a Reactor Cavity during a Steam Explosion for External Reactor Vessel Cooling vol.14, pp.12, 2016, https://doi.org/10.3390/en14123605