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1997 Fiscal Year Final Research Report Summary

Study on Two-Phase Hydrodynamic Structure of Bubble Layers under Forced Convective Subcooled Flow Boiling

Research Project

Project/Area Number 08458124
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Research Field エネルギー学一般・原子力学
Research InstitutionKYOTO UNIVERSITY

Principal Investigator

SERIZAWA Akimi  Kyoto Univ.Dept.of Nucl.Eng., Professor, 工学研究科, 教授 (10027146)

Co-Investigator(Kenkyū-buntansha) KAWARA Zensaku  Kyoto Univ.Dept.of Nucl.Eng., Instructor, 工学研究科, 助手 (10201451)
TAKAHASHI Osamu  Kyoto Univ.Dept.of Nucl.Eng., Instructor, 工学研究科, 助手 (40127098)
KATAOKA Isao  Kyoto Univ.Dept.of Nucl.Eng., Assoc.Prof., 工学研究科, 助教授 (80093219)
Project Period (FY) 1996 – 1997
KeywordsSubcooled boiling / Bubble layers / Two-phase flow structure / Critical heat flux / Film flow / Experiment / Numerical simulation / Physical models
Research Abstract

The initial research plan has been extended to cover, not only multi-fluid hydrodynamic structure of bubble layers, but also wider aspects of forced convection subcooled flow boiling and critical heat flux both experimentally and analytically. This includes (1) bubble behaviors under conditions up to the DNB point, (2) phase distribution and turbulence mechanisms in various channels, (3) 2-dimensional time-dependent film flow behavior, (4) turbulent dispersion of liquid droplets in turbulent shear flow field, awl (5) prediction of the DNB and film dryout.
Experimental observations have revealed several different mechanisms dominating bubble lateral migrations, resulting in non-uniform distributions of phases and turbulence. These general trends were successfully predicted by numerical simulations. We also developed an analytical model to numerically predict critical heat fluxes (DNB and dryout heat flux) based on multi-fluid models. In order for these models to incorporate more accurately the effects of time-dependent spatially varying film thickness and liquid droplets behavior in turbulent gas flow, we have developed a new ultrasonic echo technique with high spatial and time resolutions and a numerical simulation model to calculate deposition and turbulent diffusion of liquid droplets based on two-way coupling method. The latter method has been shown to be a good tool to objectively evaluate the validity of existing correlations.

  • Research Products

    (8 results)

All Other

All Publications (8 results)

  • [Publications] I.Kataoka et al: "Study on Analytical Prediction of Forced Convective CHF Based on Multi-Fluid Model" Nuclear Engineering and Design,. 175. 107-117 (1997)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] A.Serizawa et al.: "Experimental and Numerical Simulation of Bubbly Two-Phase Flow across Horizontal and Inclined Rod Bundles," Nuclear Engineering and Design. 175. 131-146 (1997)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] Z.Kawara et al.: "Forced Convective CHF Based on Two-Fluid and Three-Fluid Model" Heat Transfer 1998. 2. 103-108 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] T.Kamei and A.Serizawa: "Measurement of 2-Dimensional Local Instantaneous Liquid Film Thickness around Simulated Nuclear Fuel Rod by Ultrasonic Transmission Technique" Nuclear Engineering and Design. 184. 349-362 (1998)

    • Description
      「研究成果報告書概要(和文)」より
  • [Publications] I.Kataoka, S.Kodamal, A.Tomiyama and A.Serizawa: "Study on Analytical Prediction of Forced Convective CHF Based on Multi-Fluid Model" Nuclear Engineering and Design. Vol.175. 197-117 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] A.Serizawa K.Huda, Y.Yamada and I.kataoka: "Experimental and Numerical Simulation of Bubbly Two-Phase Flow across Horizontal and Inclined Rod Bundles" Nuclear Engineering and Design. Vol.175. 131-146 (1997)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] Z.Kawara, I.Kataoka, A.Serizawa, Y.J.Ko and O.Takahashi: "Forced Convective CHF Based on Two-Fluid and Three-Fluid Model" Heat Transfer 1998. Vol.2. 103-108 (1998)

    • Description
      「研究成果報告書概要(欧文)」より
  • [Publications] T.Kamei and A.Serizawa: "Measurement of 2-Dimensional Local Instantaneous Liquid Film Thickness around Simulated Nuclear Fuel Rod by Ultrasonic Transmission Technique" Nuclear Engineering and Design. Vol.184. 349-362 (1998)

    • Description
      「研究成果報告書概要(欧文)」より

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Published: 1999-12-08  

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