Nuclear Engineering and Technology

  • 제38권8호
  • /
  • Pages.733-752
  • /
  • 2006
  • /
  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

MULTI-DIMENSIONAL APPROACHES IN SEVERE ACCIDENT MODELLING AND ANALYSES

  • Fichot, F. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs) ;
  • Marchand, O. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs) ;
  • Drai, P. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs) ;
  • Chatelard, P. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs) ;
  • Zabiego, M. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs) ;
  • Fleurot, J. (Institute de Radioprotection et de Surete Nucleaire Direction de la Prevention des Accidents Majeurs)
  • 발행 : 2006.12.01
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초록

Severe accidents in PWRs are characterized by a continuously changing geometry of the core due to chemical reactions, melting and mechanical failure of the rods and other structures. These local variations of the porosity and other parameters lead to multi-dimensionnal flows and heat transfers. In this paper, a comprehensive set of multi-dimensionnal models describing heat transfers, thermal-hydraulics and melt relocation in a reactor vessel is presented. Those models are suitable for the core description during a severe accident transient. A series of applications at the reactor scale shows the benefits of using such models.

키워드

참고문헌

  1. P. Chatelard. Synthesis of the ICARE/CATHARE V1mod1 assessment. Note Technique SEMAR 02/07, IRSN, 2002
  2. P. Chatelard, J. Fleurot, O. Marchand and P. Drai. Assessment of the ICARE/CATHARE V1 severe accident code. In Proceedings of ICONE 14, 14 th International Conference on Nuclear Engineering, Miami (USA), 2006. ASME
  3. G. Repetto and S. Ederli. Analysis of the FPT0 and FPT2 Phebus FP experiments using porous medium geometry with the ICARE2 code. In 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11), Avignon, France, 2005
  4. F. Fichot, V. Kobzar, Yu. Zvonarev and P. Bousquet Melou. The use of RASPLAV results in IPSN severe accident research program. In OECD-NEA, editor, Proceedings of RASPLAV Seminar, Munich, 2000
  5. M. Zabiego, F. Fichot and P. Rubiolo. Modeling of radiative heat transfer during a PWR severe accident. Nuclear Technology, 154(2):194？214, 2006 https://doi.org/10.13182/NT06-A3728
  6. M. Kaviany. Principles of Heat Transfer in Porous Media. Springer-Verlag, 2nd edition, 1995
  7. R. Siegel and J.R. Howell. Thermal Radiation Heat Transfer. McGraw-Hill, 1972
  8. H.C. Hottel and A.F. Sarofim. Radiative transfer. McGraw-Hill Book Company, New York, 1967
  9. M.S. Sohal. A radiation heat transfer model for the SCDAP code. Nuclear Technology, 75:196-204, 1986 https://doi.org/10.13182/NT86-A33862
  10. F. Fichot, P. Chatelard, M. Barrachin, V. Guillard, S. Melis and M. Zabiego. CARE/CATHARE a computer code for analysis of severe accidents in LWRs - ICARE2 V3mod1-Description of the physical models. Note Technique SEMAR 00/03, IPSN, 2001
  11. W. Strieder. Radiation heat transport in disordered media. Advances in Water Resources, 20(2-3):171？187, 1997 https://doi.org/10.1016/S0309-1708(96)00029-2
  12. R. Viskanta, S. Chellailah and M. Moallemi. Thermal Analysis of Core Barrel Heating and Coolant Recirculation During Core Uncovery in PWR Accidents. NP 5586, EPRI, November 1987
  13. R.C. Schmidt and R.D. Gasser. Models and correlations of the DEBRIS late-phase melt progression model. Technical Report SAND93-3922, Sandia National Laboratories, 1997
  14. M.Q. Brewster. Thermal radiative transfer and properties. Wiley-Interscience Publication, New York, 1992
  15. D. Vortmeyer. Radiation in packed solids. In 6th International Heat Transfer Conference, Toronto (Canada), 1978
  16. C.L. Tien and B.L. Drolen. Thermal radiation in particulate media with dependent and independent scattering. Annual Review of Numerical Fluid Mechanics and Heat Transfer, 1:1？32, 1988
  17. P. Rubiolo. Modelisation du transfert thermique dans un milieux poreux: application aux reacteurs nucleaires en situation accidentelle. PhD thesis, Universite d'Aix-Marseille I, 2000
  18. P. Rubiolo and J.M. Gatt. Modeling of the radiative contribution to heat transfer in porous media composed of spheres or cylinders. Int. J. Therm. Sci., 41:401？411, 2002 https://doi.org/10.1016/S1290-0729(02)01332-7
  19. W. Schotte. Thermal conductivity of packed beds. A.I.Ch.E. Journal, 6:63？67, 1960 https://doi.org/10.1002/aic.690060113
  20. S. Imura and E. Takegoshi. Effect of gas pressure on the effective thermal conductivity of packed beds. Heat Transfer Japanese Research, 3(4), 1974
  21. S. Ederli. Validation of the ICARE2 V3mod1.0 late phase models against ACRR MP-1 and DC-1 experiments. Note Technique SEMAR 01/50, IPSN, 2001
  22. M. Le Roy and M. Zabiego. Validation of the ICARE2 V3mod0 software against the ACRR MP-2 experiment. Technical Report 01-27, IPSN, 2001
  23. J.C. Crestia and G. Repetto. PHEBUS FPT4: Status of posttest analysis of the debris bed behaviour with ICARE2 code. NOTE TECHNIQUE SEMAR 01/02, IPSN, 2002
  24. R.L. Cox. Radiative heat transfer in arrays of parallel cylinders. PhD thesis, University of Tennessee, Knoxville, December 1976
  25. E. Decossin. Ebullition et assechement dans un lit de particules avec production interne de chaleur: Premieres experiences et simulations numeriques en situation multidimensionnelle. Ph.D.,Institut National Polytechnique, Toulouse, Fevrier 2000
  26. M.J. Konovalikhin, Z.L. Yang, M. Amjad and B.R. Seghal. On dry-out heat flux of particle debris beds with a downcomer. In Proceedings of ICONE 8, 8th International Conference on Nuclear Engineering, Baltimore (USA), April 2000
  27. V. V. Likhanskii, A. I. Loboiko and V. O. Khoruzhii. Critical heat fluxes when boiling occurs in a non-uniform heatreleasing porous medium. Atomic Energy, 84(4):230？236, 1998 https://doi.org/10.1007/BF02415229
  28. P. Mayr, M. Burger, M. Buck, W. Schmidt and G. Lohnert. Investigations on the coolability of debris in the lower head with WABE-2D and MESOCO-2D. OECD/CSNI Workshop on In-Vessel Core Debris Retention and Coolability, March 1998
  29. M. Burger, M. Buck, W. Schmidt and W. Widmann. Validation and application of theWABA code: Investigations of constitutive laws and 2D effects on debris coolability. Nuclear Engineering and Design, 236:2164-2188, 2006 https://doi.org/10.1016/j.nucengdes.2006.03.058
  30. F. Fichot, F. Duval, N. Tregoures, C. Bechaud and M. Quintard. The impact of thermal non equilibrium and large scale 2D/3D effects on debris bed reflooding and coolability. Nuclear Engineering and Design, 236:2144？2163, 2006 https://doi.org/10.1016/j.nucengdes.2006.03.059
  31. M. Quintard and S. Whitaker. Transport in ordered and disordered porous media: volume-averaged equations, closure problems and comparison with experiment. Chemical Engineering Science, 48:2537-2564, 1993 https://doi.org/10.1016/0009-2509(93)80266-S
  32. A.E. Saez and R.G. Carbonnell. Hydrodynamic parameters for gas-liquid co-current flow in packed beds. AIChE Journal, 31:52-62, 1985 https://doi.org/10.1002/aic.690310105
  33. H.S. Lee and I. Catton. Two-phase flow in stratified porous media. In 6th Information exchange meeting on debris coolability, Los Angeles (USA), 1984 https://doi.org/10.2495/CMWR980062
  34. R.J. Lipinski. A model for cooling and dryout in particle beds. Technical Report SAND 82-0765, NUREG/CR-2646, Sandia National Labs., 1982
  35. H.C. Hardee and R.H. Nilson. Natural convection in porous media with heat generation. Nuclear Science and Engineering, 63:119-132, 1977 https://doi.org/10.13182/NSE77-A27015
  36. C. Bechaud, F. Duval, F. Fichot, M. Quintard and M. Parent. Debris bed coolability using a 3-D two phase model in a porous medium. In Proceedings of ICONE 9, 9th Interna-tional Conference on Nuclear Engineering, Nice Acropolis, France, April 2001
  37. P. Horner, A. Zeisberger and F. Mayinger. Evaporation and flow of coolant at the bottom of a particle-bed modelling relocated debris. OECD/CSNIWorkshop on In-Vessel Core Debris Retention and Coolability, March 1998
  38. M. Buck, W. Schmidt and M. Burger. Multidimensional modelling of debris bed coolability and quenching. In First ICARE/CATHARE Seminar, Cadarache, France, November 2001. IRSN
  39. F.P. Tsai, J. Jakobsson, I. Catton and V.K. Dhir. Dry-out of an inductively heated bed of steel particles with subcooled flow from beneath the bed. Nuclear Technology, 65:10？15, 1984 https://doi.org/10.13182/NT84-A33367
  40. D.O. Lee and R.H. Nilson. Flow visualization in heat generating porous media. Technical Report SAND76-0614, Sandia National Labs., 1977
  41. N. Tregoures, F. Fichot, F. Duval and M. Quintard. Multidimensional numerical study of core debris bed reflooding under severe accident conditions. In 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul (Korea), 2003
  42. S.S. Dosanjh. Melt propagation in porous media. Int. J. Heat Mass Transfer, 32(7), 1989 https://doi.org/10.1016/0017-9310(89)90036-7
  43. R.C. Schmidt. MERIS: a model for melt relocation in core structures of nuclear reactors during severe accident conditions. Technical Report NRC FIN L-2452, Sandia National Laboratories, 1993
  44. S. Whitaker. Flow in porous media II: The governing equations for immiscible, two-phase flow. Transport in Porous Media, 1:105？125, 1986 https://doi.org/10.1007/BF00714688
  45. F. A. L. Dullien. Porous Media Fluid Transport and Pore Structure. Academic Press, Inc., 1979
  46. A.E. Scheidegger. The Physics of Flow Through Porous Media. University of Toronto Press, 1974
  47. F. Fichot, M. Ortega-Bernardo and B. Lefevre. Melt relocation through a rod bundle. Note Technique SEMAR 99/34, IPSN, 1999
  48. S. S. Kutateladze. Handbook of Heat Transfer and Hydrodynamical Resistance. Energoatomizdat, 1990
  49. M. Ramacciotti. Modeles de viscosite des systemes contenant des particules en suspension. Etude bibliographique. Note Technique 98/056, CEA/DER/SERA/VULCANO, 1998
  50. M. Salay and F. Fichot. Modelling of corium stratification in the lower plenum of a reactor vessel. In OECD/NEA, editor, Proceedings of OECD MASCA Seminar, Aix en Provence (France), June 2004
  51. M. Ortega-Bernardo and F. Fichot. Post-test calculations of FPT1 test using ICARE2 V3MOD0 code : an alternative scenario. In Proceedings of ICONE 8, 8th International Conference on Nuclear Engineering, Baltimore (USA), April 2000
  52. V. Guillard, F. Fichot, P. Boudier, M. Parent and R. Roser. ICARE/CATHARE coupling : three-dimensional thermalhydraulics of LWR severe accidents. In Proceedings of ICONE 9, 9 th International Conference on Nuclear Engineering, Nice Acropolis, France, April 2001