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Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition

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초록

We measured the heat load to a reactor vessel with and without the in-vessel debris bed under an IVRERVC condition. Mass transfer methodology was adopted based on heat and mass transfer analogy to achieve high Ra0 H of order ~1015 with compact test rigs. We postulated the in-vessel debris bed has a flat top and particulate debris was simulated as an identical diameter spheres. We conducted experiments varying the height of the debris bed and the results showed that Nusselt numbers decreased in both uppermost and curved surfaces with the increasing bed height. Once the debris bed is formed, it acts as an obstacle to the natural convective flow, which reduces the buoyancy. The reduction of driving force results in the impaired heat transfer in both upward and downward heat transfers

Abstract

We measured the heat load to a reactor vessel with and without the in-vessel debris bed under an IVRERVC condition. Mass transfer methodology was adopted based on heat and mass transfer analogy to achieve high Ra0 H of order ~1015 with compact test rigs. We postulated the in-vessel debris bed has a flat top and particulate debris was simulated as an identical diameter spheres. We conducted experiments varying the height of the debris bed and the results showed that Nusselt numbers decreased in both uppermost and curved surfaces with the increasing bed height. Once the debris bed is formed, it acts as an obstacle to the natural convective flow, which reduces the buoyancy. The reduction of driving force results in the impaired heat transfer in both upward and downward heat transfers

참고문헌 (39)

  1. 박해균, "Mass Transfer Experiments for the Heat Load During In-Vessel Retention of Core Melt", Nuclear Engineering and Technology, 48(4), pp.906~914 (2016), 한국원자력학회
  2. S. H. Kim, "Heat load imposed on reactor vessels during in-vessel retention of core melts", Nucl. Eng. Des, 308, pp.1~8 (2016)
  3. H. K. Park, "Variation in the angular heat flux of the oxide pool with Rayleigh number", Ann. Nucl. Energy, 170, pp.128~135 (2017)
  4. H. K. Park, "Natural convection of melted core at the bottom of nuclear reactor vessel in a severe accident", Int. J. Energy Res, 42, pp.303~313 (2018)
  5. J. S. Park, "Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition", Ann. Nucl. Energy, 166, pp.108813~ (2022)
  6. J. L. Rempe, "In-vessel retention of molten corium : lessons learned and outstanding issues", Nucl. Technol, 161(3), pp.210~267 (2008)
  7. 정재훈, "EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION", Nuclear Engineering and Technology, 47(1), pp.66~73 (2015), 한국원자력학회
  8. O. Kymӓlӓinen, "Heat flux distribution from a volumetrically heated pool with high Rayleigh number", Nucl. Eng. Des, 149, pp.401~408 (1994)
  9. T. G. Theofanous, "The first results from the ACOPO experiment", Nucl. Eng. Des, 169, pp.49~57 (1997)
  10. B.R. Sehgal, "Natural convection heat transfer in a stratified melt pool with volumetric heat generation", 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (2004)
  11. Y. P. Zhang, "Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers e results of COPRA experiments", Prog. Nucl. Energy, 86, pp.80~86 (2016)
  12. X. Gaus-Liu, "Review of Experimental Studies on the Heat Transfer Behavior of Volumetrically Heated Pool with Different Boundary Conditions and the Influence of Crust Formation", Charlotte ICONE24 (2016)
  13. D. H. Nguyen, "Investigation of the structure of debris beds formed fuel rods fragmentation", Nucl. Eng. Des, 313, pp.96~107 (2017)
  14. F. Fichot, "The impact of thermal non-equilibrium and large-scale 2D", 3D effects on debris bed reflooding and coolability, 2006, pp.236, 2144~2163
  15. W. Ma, "In-vessel melt retention of pressurized water reactors : historical review and future research needs", Engineering, 2, pp.103~111 (2016)
  16. K. H. Lim, "Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1", Ann. Nucl. Energy, 109, pp.337~349 (2017)
  17. F. Xiaoliang, "Study on core melt process for a 1000MW reactor by external reactor vessel cooling", 8th International Topical Meeting on Nuclear Thermal-Hydraulics (2010)
  18. R. J. Park, "Effect of SAMG entry condition on operator action time for severe accident mitigation", Nucl. Eng. Des, 241, pp.1807~1812 (2011)
  19. R. J. Park, "Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC", Ann. Nucl. Energy, 89, pp.50~55 (2016)
  20. S. H. Kim, "Natural convection of the oxide pool in a threelayer configuration of core melts", Nucl. Eng. Des, 317, pp.100~109 (2017)
  21. 김수현, "Two- and three-dimensional experiments for oxide pool in in-vessel retention of core melts", Nuclear Engineering and Technology, 49(7), pp.1405~1413 (2017), 한국원자력학회
  22. S. H. Kim, "Mass transfer experiments on the natural convection heat transfer of the oxide pool in a three-layer configuration", Prog. Nucl. Energy, 106, pp.11~19 (2018)
  23. 배지원, "Development of Multi-Cell Flows in the Three-Layered Configuration of Oxide layer and Their Influence on the Reactor Vessel Heating", Nuclear Engineering and Technology, 51(4), pp.996~1007 (2019), 한국원자력학회[DOI]
  24. 배지원, "Comparisons of 2-D and 3-D IVR experiments for oxide layer in the three-layer configuration", Nuclear Engineering and Technology, 52(11), pp.2499~2510 (2020), 한국원자력학회[DOI]
  25. Y. Jin, "In- and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR", Ann. Nucl. Energy, 80, pp.322~337 (2015)
  26. A. Bejan, "Convection Heat Transfer", pp.537~595 (2003), Wiley
  27. E. J. Fenech, "Mass transfer by free convection at horizontal electrodes", Electrochim. Acta, 2, pp.311~325 (1960)
  28. V. G. Levich, "Physicochemical Hydrodynamics" (1962), Prentice-Hall
  29. M. S. Chae, "Natural convection heat transfer in a uniformly heated horizontal pipe", Heat Mass Tran, 50, pp.115~123 (2014)
  30. H. H. Ahn, "Anode influence on the electrochemical realization of packed bed heat transfer", Heat Mass Tran, 57, pp.1685~1695 (2021)
  31. H. H. Ahn, "Influences of sphere diameter and bed height on the natural convection heat transfer of packed beds", Int. J. Heat Mass Tran, 194, pp.123032~ (2022)
  32. J. Krysa, "Free convection mass transfer in open upward-facing cylindrical cavities", Chem. Eng. J, 79, pp.179~186 (2000)
  33. J. Krysa, "Free convective mass transfer at uppointing truncated cones", Chem. Eng. J, 85, pp.147~151 (2002)
  34. SANG-HYUK KO, "APPLICATIONS OF ELECTROPLATING METHOD FORHEAT TRANSFER STUDIES USING ANALOGY CONCEPT", Nuclear Engineering and Technology, 38(3), pp.251~258 (2006), 한국원자력학회
  35. J. K. Lee, "Experimental study of natural convection heat transfer in a volumetrically heated semicircular pool", Ann. Nucl. Energy, 73, pp.432~440 (2014)
  36. L. Barleon, "Cooling of debris beds", Nucl. Technol, 65, pp.67~86 (1984)
  37. T. N. Dinh, "On heat transfer characteristics of real and simulant melt pool experiments", Nucl. Eng. Des, 169, pp.151~164 (1997)
  38. W. G. Steele, "Experimental and Uncertainty Analysis for Engineers" (1999), John Wiley & Son
  39. J.M. Bonnet, "Thermal hydraulic phenomena in corium pools: the BALI experiment", 7th International Conference on Nuclear Engineering (1999)

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