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Volumn 35, Issue 6, 1998, Pages 399-405

Spacer effect model for subchannel analysis

Author keywords

Critical power; Droplet deposition; Ferrule type spacer; Fuel bundle; Spacer model; Subchannel analysis; Velocity fluctuation

Indexed keywords

BOILING WATER REACTORS; CHANNEL FLOW; DEPOSITION; MATHEMATICAL MODELS; RADIAL FLOW; REYNOLDS NUMBER; TURBULENCE; TURBULENT FLOW; VAPORS; VELOCITY MEASUREMENT;

EID: 0032094460     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.1998.9733881     Document Type: Article
Times cited : (18)

References (12)
  • 1
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    • Nishida, K.1
  • 2
    • 0008631997 scopus 로고
    • Critical power evaluation with consideration of differences in droplet behavior due to spacer shape influence
    • Kanazawa, T., et al.: Critical power evaluation with consideration of differences in droplet behavior due to spacer shape influence, J. Nucl. Sci. Technol., 32[4], 301 (1995).
    • (1995) J. Nucl. Sci. Technol. , vol.32 , Issue.4 , pp. 301
    • Kanazawa, T.1
  • 3
    • 85004246621 scopus 로고
    • Analytical prediction of CHF by FIDAS code based on film flow model
    • Sugawara, S.: Analytical prediction of CHF by FIDAS code based on film flow model, J. Nucl. Sci. Technol., 27, 12 (1990).
    • (1990) J. Nucl. Sci. Technol. , vol.27 , pp. 12
    • Sugawara, S.1
  • 4
    • 0029490073 scopus 로고
    • Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code
    • Knabe, K., Wehle, F.: Prediction of dryout performance for boiling water reactor fuel assemblies based on subchannel analysis with the RINGS code, Nucl. Technol., 112, 315 (1995).
    • (1995) Nucl. Technol. , vol.112 , pp. 315
    • Knabe, K.1    Wehle, F.2
  • 5
    • 84915299513 scopus 로고
    • Critical power analysis with multifluid model
    • [in Japanese]
    • Terasaka, H., et al.: Critical power analysis with multifluid model, Proc. 23rd Japan Heat Transfer Conf., 227 (1986), [in Japanese].
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    • Terasaka, H.1
  • 6
    • 0023362277 scopus 로고
    • On the development of turbulent flow in wall subchannel of a rod bundle
    • Rheme, K.: On the development of turbulent flow in wall subchannel of a rod bundle, Nucl. Technol., 77, 331 (1987).
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    • Rheme, K.1
  • 7
    • 85010492079 scopus 로고
    • Experimental study of single-phase flow fields around steam generator tube support plate
    • ASME
    • Bates, J. M., et al.: Experimental study of single-phase flow fields around steam generator tube support plate, “Fluid Flow and Heat Transfer over Rod or Tube Bundle”, ASME, 41 (1979).
    • (1979) Fluid Flow and Heat Transfer over Rod Or Tube Bundle , pp. 41
    • Bates, J.M.1
  • 8
    • 0003236399 scopus 로고    scopus 로고
    • The thermal-hydraulic of a boiling water nuclear reactor
    • Lahey, Jr. R. T., et al.: The thermal-hydraulic of a boiling water nuclear reactor, ANS Monograph, (1997).
    • (1997) ANS Monograph
    • Lahey, R.T.1
  • 9
    • 84958431243 scopus 로고
    • The dispersion of marked fluid in turbulent shear flow
    • Elder, J. W.: The dispersion of marked fluid in turbulent shear flow, J. Fluid Mech., 5, 544 (1959).
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  • 11
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    • Heat transfer argumentation in rod bundles near grid spacer
    • Yao, S. C., et al.: Heat transfer argumentation in rod bundles near grid spacer, J. Heat Transfer, 104, 76 (1982).
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    • Yao, S.C.1
  • 12
    • 84910427874 scopus 로고
    • Progress in thermal-hydraulics for rod and tube bundle geometries
    • ASME
    • Rowe, D. S.: Progress in thermal-hydraulics for rod and tube bundle geometries, “Fluid Flow and Heat Transferover Rod or Tube Bundle”, ASME, 1 (1979)
    • (1979) Fluid Flow and Heat Transferover Rod Or Tube Bundle , pp. 1
    • Rowe, D.S.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.