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Volumn 240, Issue 9, 2010, Pages 2148-2159

An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head

Author keywords

[No Author keywords available]

Indexed keywords

CFD MODELS; CFD SIMULATIONS; COMPUTATIONAL FLUID DYNAMICS METHODS; CONTROL ROD GUIDE TUBES; COOLABILITY; GOVERNING PARAMETERS; INTEGRAL EXPERIMENTS; MOLTEN CORIUM; NUMERICAL SIMULATION; PHASE CHANGE; SAFETY ANALYSIS; SEVERE ACCIDENT; SIMULATION RESULT; TURBULENT NATURAL CONVECTION;

EID: 77955427390     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.11.029     Document Type: Conference Paper
Times cited : (46)

References (40)
  • 1
    • 0030196878 scopus 로고    scopus 로고
    • An experimental study of natural convection in a volumetrically heated spherical pool bounded on top with a rigid wall
    • F.J. Asfia, and V.K. Dhir An experimental study of natural convection in a volumetrically heated spherical pool bounded on top with a rigid wall Nucl. Eng. Des. 163 1996 333 348
    • (1996) Nucl. Eng. Des. , vol.163 , pp. 333-348
    • Asfia, F.J.1    Dhir, V.K.2
  • 4
    • 14844336753 scopus 로고    scopus 로고
    • Modeling of heat transfer in heated-generating liquid pools by an effective diffusivity-convectivity approach
    • Rome, Italy
    • V.A. Bui, and T.N. Dinh Modeling of heat transfer in heated-generating liquid pools by an effective diffusivity-convectivity approach Proceedings of 2nd European Thermal-Sciences Conference Rome, Italy 1996 1365 1372
    • (1996) Proceedings of 2nd European Thermal-Sciences Conference , pp. 1365-1372
    • Bui, V.A.1    Dinh, T.N.2
  • 5
    • 0017494654 scopus 로고
    • Natural convection in a volumetrically heated fluid layer at high Rayleigh numbers
    • F.B. Cheung Natural convection in a volumetrically heated fluid layer at high Rayleigh numbers Int. J. Heat Mass Transf. 20 1977 499 506
    • (1977) Int. J. Heat Mass Transf. , vol.20 , pp. 499-506
    • Cheung, F.B.1
  • 6
    • 3743087881 scopus 로고
    • Modeling of heat transfer in a horizontal heat-generating layer by an effective diffusivity approach
    • F.B. Cheung, S.W. Shiah, D.H. Cho, and M.J. Tan Modeling of heat transfer in a horizontal heat-generating layer by an effective diffusivity approach ASME HTD 192 1992 55 62
    • (1992) ASME HTD , vol.192 , pp. 55-62
    • Cheung, F.B.1    Shiah, S.W.2    Cho, D.H.3    Tan, M.J.4
  • 7
    • 0031165347 scopus 로고    scopus 로고
    • Turbulence modeling for large volumetrically heated liquid pools
    • T.N. Dinh, and R.R. Nourgaliev Turbulence modeling for large volumetrically heated liquid pools Nucl. Eng. Des. 169 1997 131 150
    • (1997) Nucl. Eng. Des. , vol.169 , pp. 131-150
    • Dinh, T.N.1    Nourgaliev, R.R.2
  • 8
    • 0031166484 scopus 로고    scopus 로고
    • On heat transfer characteristics of real and simulant melt pool experiments
    • T.N. Dinh, R.R. Nourgaliev, and B.R. Sehgal On heat transfer characteristics of real and simulant melt pool experiments Nucl. Eng. Des. 169 1997 151 164
    • (1997) Nucl. Eng. Des. , vol.169 , pp. 151-164
    • Dinh, T.N.1    Nourgaliev, R.R.2    Sehgal, B.R.3
  • 9
    • 0032160951 scopus 로고    scopus 로고
    • Numerical simulation of the stratified-corium temperature field and melting of the reactor vessel for a severe accident in a nuclear power station
    • L.A. Dombrovskii, L.I. Zaichik, and Yu.A. Zeigarnik Numerical simulation of the stratified-corium temperature field and melting of the reactor vessel for a severe accident in a nuclear power station Thermal Eng. 45 9 1998 755 765
    • (1998) Thermal Eng. , vol.45 , Issue.9 , pp. 755-765
    • Dombrovskii, L.A.1    Zaichik, L.I.2    Zeigarnik . Y, A.3
  • 10
    • 0003846344 scopus 로고
    • Analysis of turbulent free convection coundary layer on flat plate
    • NACA TN 2207. Fluent Inc.
    • Eckert, E.R.G., Jackson, T.W., 1950. Analysis of turbulent free convection coundary layer on flat plate. NACA TN 2207. Fluent Inc., Fluent User's Guide, 2006.
    • (1950) Fluent User's Guide
    • Eckert, E.R.G.1    Jackson, T.W.2
  • 11
    • 51349153873 scopus 로고    scopus 로고
    • Thermal-hydraulic analysis for inversely stratified molten corium in lower vessel
    • M. Fukasawa, S. Hayakawa, and M. Saito Thermal-hydraulic analysis for inversely stratified molten corium in lower vessel J. Nucl. Sci. Technol. 45 9 2008 873 888
    • (2008) J. Nucl. Sci. Technol. , vol.45 , Issue.9 , pp. 873-888
    • Fukasawa, M.1    Hayakawa, S.2    Saito, M.3
  • 13
    • 1542678676 scopus 로고    scopus 로고
    • From canonical to complex flows: Recent progress on monotonically integrated les
    • F.F. Grinstein, and C. Fureby From canonical to complex flows: recent progress on monotonically integrated LES J. Comput. Sci. Eng. 2004 36 49
    • (2004) J. Comput. Sci. Eng. , pp. 36-49
    • Grinstein, F.F.1    Fureby, C.2
  • 14
    • 17644429486 scopus 로고    scopus 로고
    • Direct numerical and large eddy simulations in nuclear applications
    • G. Grotzbach, and M. Worner Direct numerical and large eddy simulations in nuclear applications Int. J. Heat Fluid Flow 20 1999 222 240
    • (1999) Int. J. Heat Fluid Flow , vol.20 , pp. 222-240
    • Grotzbach, G.1    Worner, M.2
  • 15
    • 0016364027 scopus 로고
    • Free convection heat transfer with internal heat source: Calculations and measurements
    • 3, NC-2.8, Tokyo, Japan
    • M. Jahn, and H.H. Reineke Free convection heat transfer with internal heat source: Calculations and measurements Proceedings of the 5th International Heat Transfer Conference 3, NC-2.8, Tokyo, Japan 1974
    • (1974) Proceedings of the 5th International Heat Transfer Conference
    • Jahn, M.1    Reineke, H.H.2
  • 16
    • 70349971077 scopus 로고    scopus 로고
    • An experimental study on debris formation with corium stimulant materials
    • Anaheim, CA, USA
    • P. Kudinov, A. Karbojian, W.M. Ma, and T.N. Dinh An experimental study on debris formation with corium stimulant materials Proceedings of ICAPP'08 Anaheim, CA, USA 2008
    • (2008) Proceedings of ICAPP'08
    • Kudinov, P.1    Karbojian, A.2    Ma, W.M.3    Dinh, T.N.4
  • 17
    • 84974159387 scopus 로고
    • Steady and transient thermal convection in a fluid layer with uniform volumetric energy sources
    • F.A. Kulacki, and A.A. Emara Steady and transient thermal convection in a fluid layer with uniform volumetric energy sources J. Fluid Mech. 83 2 1977 375 395
    • (1977) J. Fluid Mech. , vol.83 , Issue.2 , pp. 375-395
    • Kulacki, F.A.1    Emara, A.A.2
  • 18
    • 84974082044 scopus 로고
    • Thermal convection in a horizontal fluid layer with uniform volumetric energy sources
    • F.A. Kulacki, and R.J. Goldstein Thermal convection in a horizontal fluid layer with uniform volumetric energy sources J. Fluid Mech. 55 2 1972 271 287
    • (1972) J. Fluid Mech. , vol.55 , Issue.2 , pp. 271-287
    • Kulacki, F.A.1    Goldstein, R.J.2
  • 19
    • 0016508573 scopus 로고
    • Natural convection in a horizontal fluid layer with volumetric energy sources
    • F.A. Kulacki, and M.E. Nagle Natural convection in a horizontal fluid layer with volumetric energy sources Trans. ASME J. Heat Transf. 97 1975 204 211
    • (1975) Trans. ASME J. Heat Transf. , vol.97 , pp. 204-211
    • Kulacki, F.A.1    Nagle, M.E.2
  • 20
    • 0028494660 scopus 로고
    • Heat flux distribution from a volumetrically heated pool with high Rayleigh number
    • O. Kymalainen, H. Tuomisto, O. Hongisto, and T.G. Theofanous Heat flux distribution from a volumetrically heated pool with high Rayleigh number Nucl. Eng. Des. 149 1994 401 408
    • (1994) Nucl. Eng. Des. , vol.149 , pp. 401-408
    • Kymalainen, O.1    Tuomisto, H.2    Hongisto, O.3    Theofanous, T.G.4
  • 21
    • 77955431725 scopus 로고    scopus 로고
    • Fauske Associated Inc., 2
    • MAAP4 Users Manual, 1999. Fauske Associated Inc., 2.
    • (1999) MAAP4 Users Manual
  • 24
    • 0031168860 scopus 로고    scopus 로고
    • Effect of fluid Prandtl number on heat transfer characteristics in internally heated liquid pools with Rayleigh numbers up to 1012
    • R.R. Nourgaliev, T.N. Dinh, and B.R. Sehgal Effect of fluid Prandtl number on heat transfer characteristics in internally heated liquid pools with Rayleigh numbers up to 1012 Nucl. Eng. Des. 169 1997 165 184
    • (1997) Nucl. Eng. Des. , vol.169 , pp. 165-184
    • Nourgaliev, R.R.1    Dinh, T.N.2    Sehgal, B.R.3
  • 25
    • 0006800676 scopus 로고    scopus 로고
    • Simulation an analysis of transient cooldown natural convection experiments
    • R.R. Nourgaliev, T.N. Dinh, and B.R. Sehgal Simulation an analysis of transient cooldown natural convection experiments Nucl. Eng. Des. 178 1997 13 27
    • (1997) Nucl. Eng. Des. , vol.178 , pp. 13-27
    • Nourgaliev, R.R.1    Dinh, T.N.2    Sehgal, B.R.3
  • 26
    • 0031553171 scopus 로고    scopus 로고
    • An investigation of turbulence characteristics in an internally-heated unstably-stratified fluid layer
    • R.R. Nourgaliev, and T.N. Dinh An investigation of turbulence characteristics in an internally-heated unstably-stratified fluid layer Nucl. Eng. Des. 178 1997 235 258
    • (1997) Nucl. Eng. Des. , vol.178 , pp. 235-258
    • Nourgaliev, R.R.1    Dinh, T.N.2
  • 27
    • 0026971787 scopus 로고
    • Effect of outside cooling on the thermal behavior of a pressurized water reactor vessel lower head
    • H. Park, and V. Dhir Effect of outside cooling on the thermal behavior of a pressurized water reactor vessel lower head J. Nucl. Technol. 100 1992 331 346
    • (1992) J. Nucl. Technol. , vol.100 , pp. 331-346
    • Park, H.1    Dhir, V.2
  • 29
    • 77955430409 scopus 로고    scopus 로고
    • © Code manual, Report INEEL/EXT-02-00589, Revision 2.2, Idaho National Engineering and Environmental Laboratory, USA
    • © Code manual, Report INEEL/EXT-02-00589, Revision 2.2, Idaho National Engineering and Environmental Laboratory, USA.
  • 31
    • 44449152112 scopus 로고    scopus 로고
    • Heat transfer process in reactor vessel lower plenum during a late phase of in-vessel core melt progression
    • B.R. Sehgal, V.A. Bui, T.N. Dinh, and R.R. Nourgaliev Heat transfer process in reactor vessel lower plenum during a late phase of in-vessel core melt progression J. Adv. Nucl. Sci. Technol., Plenum Publ. Corp. 26 1998 103 135
    • (1998) J. Adv. Nucl. Sci. Technol., Plenum Publ. Corp. , vol.26 , pp. 103-135
    • Sehgal, B.R.1    Bui, V.A.2    Dinh, T.N.3    Nourgaliev, R.R.4
  • 34
    • 33845527584 scopus 로고    scopus 로고
    • Analysis of melt pool heat transfer in a BWR lower head
    • Albuquerque, NM, USA, November 12-18
    • C.T. Tran, and T.N. Dinh Analysis of melt pool heat transfer in a BWR lower head Transactions of ANS Winter Meeting, vol. 95 Albuquerque, NM, USA, November 12-18 2006 629 631
    • (2006) Transactions of ANS Winter Meeting, Vol. 95 , pp. 629-631
    • Tran, C.T.1    Dinh, T.N.2
  • 37
    • 55249125206 scopus 로고    scopus 로고
    • Application of the phase-change effective convectivity model to analysis of core melt pool formation and heat transfer in a BWR lower head
    • Anaheim, CA, USA
    • C.T. Tran, and T.N. Dinh Application of the phase-change effective convectivity model to analysis of core melt pool formation and heat transfer in a BWR lower head Transactions of ANS 2008 Annual Meeting Anaheim, CA, USA 2008
    • (2008) Transactions of ANS 2008 Annual Meeting
    • Tran, C.T.1    Dinh, T.N.2
  • 38
    • 68749101898 scopus 로고    scopus 로고
    • The effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head. Part I. Physical processes, modeling and model implementation
    • C.T. Tran, and T.N. Dinh The effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head. Part I. Physical processes, modeling and model implementation J. Prog. Nucl. Energy 51 8 2009 849 859
    • (2009) J. Prog. Nucl. Energy , vol.51 , Issue.8 , pp. 849-859
    • Tran, C.T.1    Dinh, T.N.2
  • 39
    • 68749101898 scopus 로고    scopus 로고
    • The effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head. Part II. Model assessment and application
    • C.T. Tran, and T.N. Dinh The effective convectivity model for simulation of melt pool heat transfer in a light water reactor lower head. Part II. Model assessment and application J. Prog. Nucl. Energy 51 8 2009 860 871
    • (2009) J. Prog. Nucl. Energy , vol.51 , Issue.8 , pp. 860-871
    • Tran, C.T.1    Dinh, T.N.2
  • 40
    • 28844495586 scopus 로고    scopus 로고
    • Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments
    • H.-G. Willschuetz, E. Altstadt, B.R. Sehgal, and F.-P. Weiss Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments Ann. Nucl. Energy 33 2006 126 148
    • (2006) Ann. Nucl. Energy , vol.33 , pp. 126-148
    • Willschuetz, H.-G.1    Altstadt, E.2    Sehgal, B.R.3    Weiss, F.-P.4


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