Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: III - Numerical Evaluation of Fluid Mixing Phenomena using Advanced Interface-Tracking Method -

Yoshida, Hiroyuki; Nagayoshi, Takuji; Takase, Kazuyuki; Akimoto, Hajime

doi:10.1299/jpes.2.250

Cited by 5 publications

(6 citation statements)

References 5 publications

(7 reference statements)

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“…TPFIT code was applied to 2-channel air-water mixing tests (Yoshida, 2007). The dimension of calculated test channel is shown in Fig.10 (a).…”

Section: Air-water Fluid Mixing Testmentioning

confidence: 99%

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Development of Two-Phase Flow Correlation for Fluid Mixing Phenomena in Boiling Water Reactor

Yoshida¹,

Takase²

2011

Computational Simulations and Applications

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“…TPFIT code was applied to 2-channel air-water mixing tests (Yoshida, 2007). The dimension of calculated test channel is shown in Fig.10 (a).…”

Section: Air-water Fluid Mixing Testmentioning

confidence: 99%

“…The TPFIT was applied to steam water fluid mixing test (Yoshida, 2007). Calculated test channels used in these simulations are shown in Fig.10 (b).…”

Section: Steam-water Fluid Mixing Under High Pressurementioning

confidence: 99%

Development of Two-Phase Flow Correlation for Fluid Mixing Phenomena in Boiling Water Reactor

Yoshida¹,

Takase²

2011

Computational Simulations and Applications

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“…TPFIT code was applied to 2-channel air-water mixing tests (Yoshida, 2007). The dimension of calculated test channel is shown in Fig.…”

Section: Air-water Fluid Mixing Testmentioning

confidence: 99%

Computational Simulations and Applications

Zhu¹

2011

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conference and colloquium presentations in 21 countries. He also served on the editorial boards of six international journals and numerous conference organizing committees. Over the last two decades, his research and education projects have been funded by over $6 million in grants from the USA federal agencies and industrial partners. ContentsPreface XIII Part Research and Numerical Algorithms in Computational Fluid Dynamics Simulations 1 Chapter Reynolds Stress Transport Modelling 3 Sharaf F. Al-Sharif Chapter Study of Some Key Issues for Applying LES to Real Engineering Problems 27 XIV Preface 9 -12), fluid heat exchange (chapter 13 -14), airborne contaminant dispersion over buildings and atmospheric flow around a re-entry capsule (chapter 15 -16), gas-solid two phase flow in long pipes (chapter 17), free surface flow around a ship hull (chapter 18), and hydrodynamic analysis of electrochemical cells (chapter 19).  Part III covers applications of non-CFD based computational simulations, including atmospheric optical communications (chapter 20), environmental studies involving climate system simulations, porous media flow, and combustion (chapter 21 -23), solidification (chapter 24), and sound field simulations for optimal acoustic effects (chapter 25). I am grateful to InTech for the opportunity to serve as the editor for this book, and I wish to sincerely thank all contributing authors around the world for their diligence in following editorial guidelines, their willingness to support open access publications, and their valuable technical contributions that made this book possible. Special thanks are due to Ms. Ana Nikolic, Mr. Zeljko Spalj, and the technical staff at InTech for their editorial efforts, detailed reviews, and professional assistance. I also would like to thank the University of Texas at Arlington for supporting my participation in this book project. Without the support from the authors, InTech staff, and the University, this book could not have become a reality.

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“…The calculation mesh size was set to 2/3 mm to satisfy the condition that the number of the calculation meshes of gap region must be more than 6 based on results of numerical simulation of air-water and steam-water two-channel fluid mixing tests (10) Then, the total number of the calculation meshes was 496,800. A non-slip wall, constant exit pressure and constant inlet velocity were selected as boundary conditions for each subchannel.…”

Section: Analysis Conditionsmentioning

confidence: 99%

Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor Using Advanced Interface Tracking Method

Yoshida

Takase

2008

JFST

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Thermal-hydraulic design of the current boiling water reactor (BWR) is performed with the subchannel analysis codes which incorporated the correlations based on empirical results including actual-size tests. Then, for the Innovative Water Reactor for Flexible Fuel Cycle (FLWR) core, an actual size test of an embodiment of its design is required to confirm or modify such correlations. In this situation, development of a method that enables the thermal-hydraulic design of nuclear reactors without these actual size tests is desired, because these tests take a long time and entail great cost. For this reason, we developed an advanced thermal-hydraulic design method for FLWRs using innovative two-phase flow simulation technology. In this study, a detailed Two-Phase Flow simulation code using advanced Interface Tracking method: TPFIT is developed to calculate the detailed information of the two-phase flow. In this paper, firstly, we tried to verify the TPFIT code by comparing it with the existing 2-channel air-water mixing experimental results. Secondary, the TPFIT code was applied to simulation of steam-water two-phase flow in a model of two subchannels of a current BWRs and FLWRs rod bundle. The fluid mixing was observed at a gap between the subchannels. The existing two-phase flow correlation for fluid mixing is evaluated using detailed numerical simulation data. This data indicates that pressure difference between fluid channels is responsible for the fluid mixing, and thus the effects of the time average pressure difference and fluctuations must be incorporated in the two-phase flow correlation for fluid mixing. When inlet quality ratio of subchannels is relatively large, it is understood that evaluation precision of the existing two-phase flow correlations for fluid mixing are relatively low.

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Development of Design Technology on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles: III - Numerical Evaluation of Fluid Mixing Phenomena using Advanced Interface-Tracking Method -

Cited by 5 publications

References 5 publications

Development of Two-Phase Flow Correlation for Fluid Mixing Phenomena in Boiling Water Reactor

Development of Two-Phase Flow Correlation for Fluid Mixing Phenomena in Boiling Water Reactor

Computational Simulations and Applications

Numerical Evaluation of Fluid Mixing Phenomena in Boiling Water Reactor Using Advanced Interface Tracking Method

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