메뉴 건너뛰기




Volumn 166, Issue 2, 1996, Pages 147-163

Debris interactions in reactor vessel lower plena during a severe accident I. Predictive model

Author keywords

[No Author keywords available]

Indexed keywords

CREEP; FAILURE ANALYSIS; HEAT CONVECTION; HEAT FLUX; HEAT RADIATION; JETS; MASS TRANSFER; MATHEMATICAL MODELS; NUSSELT NUMBER; PRESSURE VESSELS;

EID: 0030566057     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/0029-5493(96)01269-1     Document Type: Article
Times cited : (31)

References (29)
  • 2
    • 0043038644 scopus 로고
    • Dependence of debris bed dryout heat flux on particle diameter
    • L. Barleon and H. Werle, Dependence of debris bed dryout heat flux on particle diameter, ANS Trans. 38 (1981) 382-383.
    • (1981) ANS Trans. , vol.38 , pp. 382-383
    • Barleon, L.1    Werle, H.2
  • 4
    • 0042037049 scopus 로고    scopus 로고
    • Breakup of melt jets as pre-condition for premixing: Modeling an experimental verification
    • Santa Barbara, CA, January
    • M. Burger, S.H. Cho, E.V. Berg and A. Schatz, Breakup of melt jets as pre-condition for premixing: modeling an experimental verification, OECD-NEA CSNI-FCI Specialist Meet., Santa Barbara, CA, January 1993.
    • OECD-NEA CSNI-FCI Specialist Meet. , pp. 1993
    • Burger, M.1    Cho, S.H.2    Berg, E.V.3    Schatz, A.4
  • 6
    • 0024919579 scopus 로고
    • The three mile island unit 2 core relocation - Heat transfer and mechanism
    • M. Epstein and H.K. Fauske, The Three Mile Island Unit 2 core relocation - heat transfer and mechanism, Nucl. Technol. 87 (1989) 1021-1035.
    • (1989) Nucl. Technol. , vol.87 , pp. 1021-1035
    • Epstein, M.1    Fauske, H.K.2
  • 7
    • 24244438224 scopus 로고
    • Experiments to address lower plenum response under severe accident conditions
    • R.J. Hammersly and R.E. Henry, Experiments to address lower plenum response under severe accident conditions, EPRI Rep. TR-103389, Vois. 1 and 2, 1993.
    • (1993) EPRI Rep. TR-103389 , vol.1-2
    • Hammersly, R.J.1    Henry, R.E.2
  • 9
    • 0041535811 scopus 로고
    • Cooling of debris beds - Methods of analysis for LWR safety assessments
    • Chicago, IL, August-September
    • R.E. Henry, M. Epstein and H.K. Fauske, Cooling of debris beds - methods of analysis for LWR safety assessments, Proc. Int. Meet, on Thermal Reactor Safety, Chicago, IL, August-September 1982b, 1421-1432.
    • (1982) Proc. Int. Meet, on Thermal Reactor Safety , pp. 1421-1432
    • Henry, R.E.1    Epstein, M.2    Fauske, H.K.3
  • 12
    • 0041535812 scopus 로고
    • IDCOR, debris coolability, vessel penetration, and debris dispersal
    • Fauske and Associates, Inc., Burr Ridge, IL
    • IDCOR, Debris coolability, vessel penetration, and debris dispersal, Tech. Rep. 15.2B, Fauske and Associates, Inc., Burr Ridge, IL, 1983.
    • (1983) Tech. Rep. 15.2B
  • 13
    • 0043038640 scopus 로고
    • Ph.D. Dissertation, Chemical Engineering Department, Northwestern University, Evanston, IL
    • S.W. Jones, A study of dryout heat fluxes, Ph.D. Dissertation, Chemical Engineering Department, Northwestern University, Evanston, IL, 1982.
    • (1982) A Study of Dryout Heat Fluxes
    • Jones, S.W.1
  • 14
    • 0009996121 scopus 로고
    • A particle-bed dryout model with upward and downward boiling
    • R.J. Lipinski, A particle-bed dryout model with upward and downward boiling. ANS Trans. 35 (1980) 358-360.
    • (1980) ANS Trans. , vol.35 , pp. 358-360
    • Lipinski, R.J.1
  • 15
    • 24544451782 scopus 로고
    • prepared by Fauske and Associates, Inc., Burr Ridge, IL for the Electric Power Research Institute, Palo Alto, CA
    • MAAP4, Modular Accident Analysis Program for LWR Power Plants, Vols. 1-4, prepared by Fauske and Associates, Inc., Burr Ridge, IL for the Electric Power Research Institute, Palo Alto, CA, 1994.
    • (1994) MAAP4, Modular Accident Analysis Program for LWR Power Plants , vol.1-4
  • 17
    • 0020129275 scopus 로고
    • Critical heat flux during natural convective boiling in vertical rectangular channels submerged in saturated liquid
    • M. Monde, H. Kusuda and H. Uehara, Critical heat flux during natural convective boiling in vertical rectangular channels submerged in saturated liquid, J. Heat Transfer 104 (1982) 300-303.
    • (1982) J. Heat Transfer , vol.104 , pp. 300-303
    • Monde, M.1    Kusuda, H.2    Uehara, H.3
  • 18
    • 84916304539 scopus 로고
    • Spalding, measurements of entrainment by axisymmetrical turbulent jets
    • F.B. Ricou and D.B. Spalding, Measurements of entrainment by axisymmetrical turbulent jets, J. Fluid Mech. 11 (1961) 21-32.
    • (1961) J. Fluid Mech. , vol.11 , pp. 21-32
    • Ricou, F.B.1
  • 19
    • 0019902527 scopus 로고
    • Affect of debris bed pressure, particle size and distribution on degraded nuclear reactor core coolability
    • D. Squarer, A.T. Pieczynski and L.E. Hochreiter, Affect of debris bed pressure, particle size and distribution on degraded nuclear reactor core coolability, Nucl. Sci. Eng. 80 (1982) 2.
    • (1982) Nucl. Sci. Eng. , vol.80 , pp. 2
    • Squarer, D.1    Pieczynski, A.T.2    Hochreiter, L.E.3
  • 20
    • 0028419313 scopus 로고
    • Rod bundle thermal hydraulic and melt progression analysis of CORA severe fuel damage experiments
    • K.Y. Suh, Rod bundle thermal hydraulic and melt progression analysis of CORA severe fuel damage experiments, Nucl. Sci. Eng. 116 (1994a) 245-268.
    • (1994) Nucl. Sci. Eng. , vol.116 , pp. 245-268
    • Suh, K.Y.1
  • 21
    • 0028454957 scopus 로고
    • Modeling of heat transfer to nuclear steam supply system heat sinks and application to severe accident sequences
    • K.Y. Suh, Modeling of heat transfer to nuclear steam supply system heat sinks and application to severe accident sequences, Nucl. Technol. 106 (1994b) 274-291.
    • (1994) Nucl. Technol. , vol.106 , pp. 274-291
    • Suh, K.Y.1
  • 22
    • 0028539381 scopus 로고
    • Integral analysis of debris material and heat transport in reactor vessel lower plenum
    • K.Y. Suh and R.E. Henry, Integral analysis of debris material and heat transport in reactor vessel lower plenum, Nucl. Eng. Des. 151(1) (1994c) 203-221.
    • (1994) Nucl. Eng. Des. , vol.151 , Issue.1 , pp. 203-221
    • Suh, K.Y.1    Henry, R.E.2
  • 23
    • 0041535820 scopus 로고
    • SONATA-IV: Simulation of naturally arrested thermal attack in vessel - Visualization study using Pyrex belljar and copper hemisphere heater
    • Bethesda, MD, May
    • K.Y. Suh, SONATA-IV: Simulation Of Naturally Arrested Thermal Attack In Vessel - visualization study using Pyrex belljar and copper hemisphere heater, Cooperative Severe Accident Research Program (CSARP) Semiann. Review Meet., Bethesda, MD, May 1995a.
    • (1995) Cooperative Severe Accident Research Program (CSARP) Semiann. Review Meet.
    • Suh, K.Y.1
  • 24
    • 0042537867 scopus 로고
    • CAMPFIRE-2000: Comprehensive accident management program featuring innovative research & engineering for the year 2000 and beyond
    • Niantic, CT. June
    • K.Y. Suh, C.K. Park and K.J. Yoo, CAMPFIRE-2000: Comprehensive Accident Management Program Featuring Innovative Research & Engineering for the Year 2000 and Beyond, OECD Specialist Meet. on Severe Accident Management Implementation, Niantic, CT. June 1995b.
    • (1995) OECD Specialist Meet. on Severe Accident Management Implementation
    • Suh, K.Y.1    Park, C.K.2    Yoo, K.J.3
  • 25
    • 0042037048 scopus 로고
    • In pursuit of naturally arrested thermal attack on reactor vessel during a severe accident
    • Issy-les-Moulineaux, September
    • K.Y. Suh, C.K. Park and K.J. Yoo, In pursuit of naturally arrested thermal attack on reactor vessel during a severe accident, OECD-NEA CSNI PWG 4 & 2 Meet., Issy-les-Moulineaux, September 1995c.
    • (1995) OECD-NEA CSNI PWG 4 & 2 Meet.
    • Suh, K.Y.1    Park, C.K.2    Yoo, K.J.3
  • 26
    • 0030566021 scopus 로고    scopus 로고
    • Debris interactions in reactor vessel lower plena during a severe accident II. Integral analysis
    • K.Y. Suh and R.E. Henry, Debris interactions in reactor vessel lower plena during a severe accident II. Integral analysis, Nucl. Eng. Des. 166 (2) (1996) 165-178.
    • (1996) Nucl. Eng. Des. , vol.166 , Issue.2 , pp. 165-178
    • Suh, K.Y.1    Henry, R.E.2
  • 29
    • 0043038641 scopus 로고
    • prepared as part of the OECD-NEA-TMI-2 Vessel Investigation Project for the Division of Systems Research, Office of Nuclear Regulatory Research, USNRC
    • J.R. Wolf and J.L. Rempe, TMI-2 vessel investigation project, TMI V(93)EG10, INEL Rep. prepared as part of the OECD-NEA-TMI-2 Vessel Investigation Project for the Division of Systems Research, Office of Nuclear Regulatory Research, USNRC, 1993.
    • (1993) TMI-2 Vessel Investigation Project, TMI V(93)EG10, INEL Rep.
    • Wolf, J.R.1    Rempe, J.L.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.