Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle

Koizumi, Yasuo; Kumamaru, Hiroshige; Yonomoto, Taisuke; Tasaka, Kanji

doi:10.1016/0029-5493(87)90117-8

Cited by 14 publications

(3 citation statements)

References 9 publications

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“…The HTC for much higher superheat approaches the correlation by Dougall-Rohsenow or Groeneveld 5.9 which is applicable to a fully developed film boiling of a dispersed flow. Although the Koizumi et al 23) and Sugawara 24) correlations predict the overall data trend well, both correlations tend to overestimate under conditions with higher mass fluxes.…”

Section: Htcmentioning

confidence: 95%

Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs

Sibamoto

Maruyama

Yonomoto

et al. 2011

Journal of Nuclear Science and Technology

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A heat transfer coefficient (HTC) model was developed for the prediction of post-boiling transition (post-BT) behavior that might occur during anticipated operational occurrences (AOOs) for boiling water reactors (BWRs). The model development was based on measurements of heat transfer coefficient, liquid droplet deposition rate, and droplet concentration in our experiments conducted at high pressure. The model focused on the heat transfer near the rewetting front where the cooling by droplet deposition significantly affects the propagation behavior of a liquid film. The correlation by Sugawara was validated for the prediction of the deposition by using the experimental data. The model was also expressed as a function of the distance from the rewetting front to use in analytical models for the rewetting propagation. Both expressions of the present model successfully predicted our experimental data simulating the BWR thermal-hydraulic conditions.

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Section: Htcmentioning

confidence: 95%

Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs

Sibamoto

Maruyama

Yonomoto

et al. 2011

Journal of Nuclear Science and Technology

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“…Upward steam-water dispersed flow was studied in Koizumi, et al, experiments [20]. The experiments were performed for two set-ups: one rod in a channel (the heated rod in this case was located in a circular pipe, the pipe and the rod being coaxial) and a bundle of 25 rods in a channel of square cross-section.…”

Section: Koizumi Et Al Experimentsmentioning

confidence: 99%

Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis

Ustinenko¹,

Samigulin²,

Иоилев³

et al. 2008

Nuclear Engineering and Design

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“…Koizumi et al, 1987;Moon et al, 2005;Tuzla et al, 1992). The influence of flow obstacles on post-dryout heat transfer at BWR conditions was investigated in an annular test section with a single spacer grid cell and a significant improvement of heat transfer coefficient was reported (Anglart and Persson, 2007).…”

Section: Introductionmentioning

confidence: 99%

Experimental investigation of post-dryout heat transfer in annuli with flow obstacles

Anghel

Anglart

Hedberg

2012

Nuclear Engineering and Design

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a b s t r a c tAn experimental study on post-dryout heat transfer was conducted in the High-pressure WAter Test (HWAT) loop at the Royal Institute of Technology in Stockholm, Sweden. The objective of the experiments was to investigate the influence of flow obstacles on the post-dryout heat transfer. The investigated operational conditions include mass flux equal to 500 kg/m 2 s, inlet sub-cooling 10 K and system pressure 5 and 7 MPa. The experiments were performed in annuli in which the central rod was supported with five pin spacers. Two additional types of flow obstacles were placed in the exit part of the test section: a cylinder supported on the central rod only and a typical BWR grid spacer cell. The measurements indicate that flow obstacles improve heat transfer in the boiling channel. It has been observed that the dryout power is higher when additional obstacles are present. In addition the wall temperature in post-dryout heat transfer regime is reduced due to increased turbulence and drop deposition. The present data can be used for validation of computational models of post-dryout heat transfer in channels with flow obstacles.

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Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle

Cited by 14 publications

References 9 publications

Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs

Core Heat Transfer Coefficients Immediately Downstream of the Rewetting Front during Anticipated Operational Occurrences for BWRs

Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis

Experimental investigation of post-dryout heat transfer in annuli with flow obstacles

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