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Tetsuhiro Ozaki

Observed names: Ozaki Tetsuhiro, Tetsuhiro OZAKI
ORCID: 0000-0002-0809-9864
Observed ORCID: 0000-0002-0809-9864
OpenAlex ID: A5070283161
Drift-flux correlation for rod bundle geometries
2014 · Collin Clark, Matthew Griffiths, et al. · International Journal of Heat and Fluid Flow · 70
Drift-flux model for rod bundle geometry
2015 · Tetsuhiro Ozaki, Takashi Hibiki · Progress in Nuclear Energy · 68
Development of drift-flux model based on 8 × 8 BWR rod bundle geometry experiments under prototypic temperature and pressure conditions
2013 · Tetsuhiro Ozaki, Riichiro Suzuki, et al. · Journal of Nuclear Science and Technology · 66
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Channel size effect on drift-flux parameters for adiabatic and boiling two-phase flows
2021 · Takashi Hibiki, Peng Ju, et al. · International Journal of Heat and Mass Transfer · 26
Modeling of distribution parameter, void fraction covariance and relative velocity covariance for upward steam-water boiling flow in vertical rod bundle
2017 · Tetsuhiro Ozaki, Takashi Hibiki · Journal of Nuclear Science and Technology · 26
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Modeling of void fraction covariance and relative velocity covariance for upward boiling flow in vertical pipe
2017 · Takashi Hibiki, Tetsuhiro Ozaki · International Journal of Heat and Mass Transfer · 24
Development of void fraction-quality correlation for two-phase flow in horizontal and vertical tube bundles
2017 · Takashi Hibiki, Keyou Mao, et al. · Progress in Nuclear Energy · 20
Constitutive equations for vertical upward two-phase flow in rod bundle
2018 · Takashi Hibiki, Tetsuhiro Ozaki, et al. · International Journal of Heat and Mass Transfer · 18
Modeling of distribution parameters for upward steam-water boiling flows in subchannels of a vertical rod bundle
2023 · Tetsuhiro Ozaki, Takashi Hibiki · Journal of Nuclear Science and Technology · 12
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Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow
2018 · Takashi Hibiki, Joshua P. Schlegel, et al. · Progress in Nuclear Energy · 11
Code performance with improved two-group interfacial area concentration correlation for one-dimensional forced convective two-phase flow simulation
2018 · Tetsuhiro Ozaki, Takashi Hibiki, et al. · Journal of Nuclear Science and Technology · 9
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Void fraction covariance and relative velocity covariance for steam-water boiling flows in NUPEC Type I and Type II rod bundles
2024 · Hengwei Zhang, Tetsuhiro Ozaki, et al. · International Journal of Heat and Mass Transfer · 7
Effect of interfacial drag force model on code prediction for upward adiabatic two-phase bubbly flow in vertical channels
2020 · Takashi Hibiki, Tetsuhiro Ozaki · Experimental and Computational Multiphase Flow · 7
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Development of one-dimensional two-fluid model with consideration of void fraction covariance effect
2018 · Tetsuhiro Ozaki, Takashi Hibiki, et al. · Journal of Nuclear Science and Technology · 7
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Modeling of void fraction covariance and relative velocity covariance for upward boiling flows in subchannels of a vertical rod bundle
2023 · Takashi Hibiki, Tetsuhiro Ozaki · International Journal of Heat and Mass Transfer · 6
Effect of void fraction covariance on two-fluid model based code calculation in pipe flow
2018 · Tetsuhiro Ozaki, Takashi Hibiki, et al. · Progress in Nuclear Energy · 5
Sensitivity analysis using improved two-fluid model-based 1D code with the state-of-the-art constitutive equations for two-phase flow in rod bundle
2022 · Tetsuhiro Ozaki, Takashi Hibiki, et al. · Experimental and Computational Multiphase Flow · 4
Mapping method to model subchannel distribution parameter for steam-water boiling flows in rod bundles
2025 · Hengwei Zhang, Tetsuhiro Ozaki, et al. · International Journal of Heat and Mass Transfer · 3
Effect of interfacial area concentration on one-dimensional code simulation of adiabatic two-phase flows in vertical large size channels
2021 · Tetsuhiro Ozaki, Takashi Hibiki · Nuclear Engineering and Design · 3
Thermal-hydraulic constitutive equations implemented in the system analysis code AMAGI for nuclear power reactor
2021 · Takashi Hibiki, Tetsuhiro Ozaki · Progress in Nuclear Energy · 3
Improvement of Two-Fluid Model Based 1D Code with the State-of-the-Art Constitutive Equations for Two-Phase Flow in Rod Bundle
2020 · Tetsuhiro OZAKI, Takashi HIBIKI, et al. · JAPANESE JOURNAL OF MULTIPHASE FLOW · 3
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Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codes
2016 · Tetsuhiro Ozaki, Naofumi Tsukamoto, et al. · Progress in Nuclear Energy · 3
Modeling of Sub-Channel Scale Distribution Parameter and Its Validation Based on Database of Rod Bundle Void Fraction Measurement Test Under Prototypic BWR Conditions
2021 · Tetsuhiro OZAKI, Takashi HIBIKI · JAPANESE JOURNAL OF MULTIPHASE FLOW · 2
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Modeling axial void fraction profile for subcooled boiling flow in rod bundles under atmospheric to high-pressure conditions
2025 · Tetsuhiro Ozaki, Takashi Hibiki · Journal of Nuclear Science and Technology · 1
Effect of unheated rods on subchannel average distribution parameter for steam-water boiling flows in a rod bundle
2025 · Tetsuhiro Ozaki, Takashi Hibiki · International Journal of Heat and Mass Transfer · 1
Works count: 35
Citation count: 406
H-index: 10
I10-index: 10
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