Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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CORIUM BEHAVIOR IN THE LOWER PLENUM OF THE REACTOR VESSEL UNDER IVR-ERVC CONDITION: TECHNICAL ISSUES

  • Received : 2012.03.28
  • Published : 2012.04.25
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Abstract

Corium behavior in the lower plenum of the reactor vessel during a severe accident is very important, as this affects a failure mechanism of the lower head vessel and a thermal load to the outer reactor vessel under the IVR-ERVC (In-Vessel corium Retention through External Reactor Vessel Cooling) condition. This paper discusses the state of the art and technical issues on corium behavior in the lower plenum, such as initial corium pool formation characteristics and its transient behavior, natural convection heat transfer in various geometries, natural convection heat transfer with a phase change of melting and solidification, and corium interaction with a lower head vessel including penetrations of the ICI (In-Core Instrumentation) nozzle are discussed. It is recommended that more detailed analysis and experiments are necessary to solve the uncertainties of corium behavior in the lower plenum of the reactor vessel.

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References

  1. J. L. Rempe, K. Y. Suh, F. B. Cheung, S. B. Kim, "In-Vessel Retention of Molten Corium: Lesson Learned and Outstanding issues," Nuclear Technology. 161(2008).
  2. T. G. Theofanous, C. Liu, S. Addition, S. Angelini, O. Kymalainen, and T. Salimassi, "In-Vessel Coolability and Retention of a Core Melt," Nuclear Engineering & Design, 169(1997).
  3. H. Esmaili, M. Khatib-Rahbar, "Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction," NUREG/CR-6849, ERI/NRC 04-201 (2004).
  4. T. G. Theofanous, C. Liu, S. Addition, S. Angelini, O. Kymalainen, and T. Salmassi, "In-Vessel Coolability and Retention of a Core Melt," DOE/ID-10460, Vol. 1&2(1995).
  5. O. Kymalainean, H. Tuomisto, T. G. Theofanous, "In- Vessel Retention of Corium at the Loviisa Plant", Nuclear Engineering & Design, 169, 109-130 (1997). https://doi.org/10.1016/S0029-5493(96)01280-0
  6. M. Fisher, P. Levi, G. Langrock, "The Impact of Thermal Chemical Phenomena on the Heat Fluxes into the RPV during In-Vessel Melt Retention," ICAPP2011, Nice, France(2011).
  7. J. W. Park, D. W. Jeong, "An Investigation of Thermal Margin for External Reactor Vessel Cooling (ERVC) in Large Advanced Light Water Reactors (ALWR)", Proceedings of the KNS, Kwangju, Korea(1997).
  8. R. J. Park, K. S. Ha, S. B. Kim, H. D. Kim, "Two-Phase Natural Circulation Flow of Air and Water in a Reactor Cavity Model under External Reactor Vessel Cooling during a Severe Accident", Nuclear Engineering and Design, 236, 2424-2430 (2006). https://doi.org/10.1016/j.nucengdes.2006.03.006
  9. J W. Park et al., "Design for the In-Vessel Core Melt Retention and the Overall Severe Accident Strategy of the APR1400," ICAPP '05, Seoul, Korea(2005).
  10. R. E. Henry, H. K. Fauske, "External Cooling of a Reactor Vessel under Severe Accident Conditions", Nuclear Engineering & Design, 139, 31-43 (1993). https://doi.org/10.1016/0029-5493(93)90260-G
  11. S. H. Yang, W. P. Baek, S. H. Chang, "An Experimental Study of Pool-Boiling CHF on Downward Facing Plates", J. of KNS, 26, 493-501 (1994).
  12. ] T. Y. Chu, "Ex-vessel Boiling Experiments; Laboratoryand Reactor-scale Testing of the Flooded Cavity Concept for In-Vessel Core Retention Part II: Reactor-scale Boiling Experiments of the Flooded Cavity Concept for In-Vessel Core Retention", Nuclear Engineering & Design, 169, 89-99 (1997). https://doi.org/10.1016/S0029-5493(96)01279-4
  13. H. Schmidt, "Large Scale Verification of External RPV Cooling in Case of Severe Accident", ICAPP'04, Pittsburgh, PA, USA, June 13-17 (2004).
  14. T.G. Theofanous and S. Syri, "The Coolability Limits of a Reactor Pressure Vessel Lower Head," Nuclear Engineering and Design, 169, 59-76(1997). https://doi.org/10.1016/S0029-5493(97)00024-1
  15. J. H. Scobel, T. G. Theofanous, and L. E. Conway, "In-Vessel Retention of Molten Core Debris in the Wastinghouse AP1000 Advanced Passive PWR," ICAPP'02, Hollywood, Florida, USA,(2002).
  16. T. N. Dinh, J. P. Tu, and T. G. Theofanous, "Two-Phase Natural Circulation Flow in AP-1000 In-Vessel Retention- Related ULPU-V Facility Experiments," ICAPP'04, Pittsburgh, PA USA(2004).
  17. J. M. Bonnet, S. Rouge, J. M. Seiler, "Large Scale Experiments for Core Melt Retention: BALI: Corium Pool Thermo hydraulics, SULTAN: Boiling under Natural Convection", OECD/CSNI/NEA Workshop on Large Molten Pool Heat Transfer, Grenoble, France (1994).
  18. S. Rouge, "SULTAN Test Facility for Large-Scale Vessel Coolability in Natural Convection at Low Pressure", Nuclear Engineering & Design, 169, 185-195 (1997). https://doi.org/10.1016/S0029-5493(96)01277-0
  19. M. Barrachin and F. Defoort, "Thermophysical Properties of In-Vessel Corium: MASCA Programme Related Results," Proceedings of MASCA Seminar 2004, Aix-en-Provence, France (2004).
  20. J. M. Seiler et al., "Consequences of Physico-Chemistry Effects on In-Vessel Retention Issue," NURETH-11, Avignon, France(2005).
  21. L. J. Siefken et al., "SCDAP/RELAP5/MOD3.3 Code Manual, Vol. I-V," NUREG/CR-6150 (2001).
  22. R. J. Park, S. B. Kim, K. Y. Suh, J. L. Rempe and F. B. Cheung, "Detailed Analysis of a Late-Phase Core Melt Progression for the Evaluation of In-Vessel Corium Retention," Nuclear Technology, 156(2006).
  23. Cheynet et al., "Thermosuite," Calphad 26(2), 167 - 174 (2002). https://doi.org/10.1016/S0364-5916(02)00033-0
  24. K. H. Kang, R. J. Park, S. W. Hong, "Thermodynamic Analysis for the Three-layered Melt Pool during the Severe Accidents in the APR1400," NURETH-13, Kanazawa City, Ishikawa Prefecture, Japan(2009).
  25. T. H. Fan and F. B. Cheung, "Modeling of Transient Turbulent Natural Convection in a Melt Layer Solidification" J. of Heat Transfer, 119, 544-552(1997). https://doi.org/10.1115/1.2824137
  26. F. B. Cheung, "Periodic Growth and Decay of a Frozen Crust over a Heat Generating Liquid Layer," J. of Heat Transfer, 103, 369-375(1981). https://doi.org/10.1115/1.3244468
  27. R. J. Park, S. M. Choi, S. B. Kim, and H. D. Kim, "Natural Convection Heat Transfer with Crust Formation in the Molten Metal Pool," Nuclear Technology, 127(1), 66- 80(1999). https://doi.org/10.13182/NT99-A2984
  28. R. J. Park, S. M. Choi, S. B. Kim, and H. D. Kim, "Natural Convection Heat Transfer of the Low Prandtl Number Fluid with Solidified Layer Formation," Int. Communications in Heat and Mass Transfer, 25(8), 1065-1074(1998). https://doi.org/10.1016/S0735-1933(98)00097-9
  29. S. Globe and D. Dropkin, "Natural Convection Heat Transfer in Liquid Confined by Two Horizontal Plates and Heated From Below, " J. of Heat Transfer, 97, 24-28 (1959).
  30. H. T. Rossby, "A Study of Benard Convection with and without Rotation," J. of Fluid Mech., 36, 309-335(1969). https://doi.org/10.1017/S0022112069001674
  31. D. C. Threlfall, "Free Convection in Low-Temperature Gaseous Helium," J. of Fluid Mech., 67, 17-28(1975). https://doi.org/10.1017/S0022112075000158
  32. F. Heslot, B. Castaing, and A. Libchabre, "Transitions to Turbulence in Helium Gas," Phys. Rev., A 36, 5870-5873 (1987).
  33. T. Y. Chu and R. J. Goldstein, "Turbulent Convection in a Horizontal Layer of Water," J. of Fluid Mech., 60, 141- 159 (1973). https://doi.org/10.1017/S0022112073000091
  34. Jae-Sun Cho, R. J. Park et al., "Enhanced Natural Convection in a Metal layer Cooled by Boiling Water," Nuclear Technology," 148 (2004).
  35. S. Cho, K. Y. Suh, C. H. Chung, R. J. Park, and S. B. Kim, "The Effect of Coolant Boiling on the Molten Metal Pool Heat Transfer with Local Solidification," J. of KNS, 32(1), 34-45(2000).
  36. J. L. Rempe, S. A. Chavez, G. L. Allison, G. E. Korth, R. J. Witt, J. J. Sienicki, S. K. Wang, L. A. Stickler, C. H. Heath, and S. D. Snow, "Light Water Reactor Lower Head Failure Analysis," NUREG/CR-5642, EGG-2618(1993).
  37. J. R. Wolf, J. L. Rempe, L. A. Stickler, G. E. Korth, D. R. Diercks, L. A. Neimark, D. W. Akers, B. K. Schuetz, S. A. Chavez, G. L. Thinners, R. J. Witt, M. L. Corradini, and J. A. Kos, "TMI-2 Vessel Investigation Report," NUREG/ CR-6197, EGG-2734(1994).
  38. S.V. Bechta, V.B. Khabensky., S.A. Vitol, E.V. Krushinov, V.S. Granovsky, D.B. Lopukh, V.V. Gusarov, A.P. Martinov, V.V. Martinov, G. Fieg, W. Tromm, D. Bottomley, H. Tuomisto, "Corrosion of vessel steel during its interaction with molten corium. Part 1: Experimental" Nuclear Engineering & Design, 236, 1810-1829(2006). https://doi.org/10.1016/j.nucengdes.2005.12.011
  39. S.V. Bechta, V.B. Khabensky., S.A. Vitol, E.V. Krushinov, V.S. Granovsky, D.B. Lopukh, V.V. Gusarov, A.P. Martinov, V.V. Martinov, G. Fieg, W. Tromm, D. Bottomley, H. Tuomisto, "Corrosion of vessel steel during its interaction with molten corium. Part 2: Model development", Nuclear Engineering & Design, 236, 1362-1370(2006). https://doi.org/10.1016/j.nucengdes.2005.12.008
  40. R. J. Park, K. H. Kang, J. T. Kim, K. Y. Lee, and S. B. Kim, "Experimental and Analytical Studies on the Penetration Integrity under External Vessel Cooling," Nuclear Technology, 145(2004).
  41. K. H. Kang, R. J. Park, J. T. Kim, K. Y. Lee, and S. B. Kim, "Thermal Behavior of the Reactor Vessel Penetration under External Vessel Cooling during a Severe Accident," Nuclear Technology, 145(2004).
  42. R. J. Hammersley and R. E. Henry, "Experiments to Address Lower Plenum Response Under Severe Accident Conditions, " EPRI Report TR-103389-V2P1, Vol. 1&2 (1994).
  43. R. C. Cripps, H. Hirschmann, B. S. Jackel, J. A. Patorski, and H. P. Seifert, "CORVIS Project - State of Progress CORVIS Report," PSI Technical Report TM-49-95-03 (1995).
  44. T. Y. Chu, M. M. Pilch, J. H. Bentz, J. S. Ludwigsen, WY Lu and L. L. Humperies, "Lower Head Failure Experiment and Analyses," NUREG/CR-5582, SAND98-2047, (1999).

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