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Michio MURASE

Observed names: M. Murase, Michio Murase, Murase, Michio
ORCID: 0000-0002-4253-0750
Observed ORCID: 0000-0002-4253-0750
OpenAlex ID: A5030343366
Experimental study of air–water two-phase flow in an 8×8 rod bundle under pool condition for one-dimensional drift-flux analysis
2011 · Shao-Wen Chen, Yang Liu, et al. · International Journal of Heat and Fluid Flow · 69
One-dimensional drift-flux model for two-phase flow in pool rod bundle systems
2011 · Shao-Wen Chen, Yang Liu, et al. · International Journal of Multiphase Flow · 67
Evaporation and condensation heat transfer with a noncondensable gas present
1993 · M. Murase, Y. Kataoka, et al. · Nuclear Engineering and Design · 60
Correlation for countercurrent flow limitation in a PWR hot leg
2012 · Michio Murase, Akio Tomiyama, et al. · Journal of Nuclear Science and Technology · 57
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Measurement of Condensation Heat Transfer Coefficient inside a Vertical Tube in the Presence of Noncondensable Gas
1995 · Hidefumi AKAKI, Yoshiyuki KATAOKA, et al. · Journal of Nuclear Science and Technology · 56
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Development of Simplified Wave-type Vane in BWR Steam Dryer and Assessment of Vane Droplet Removal Characteristics
1999 · Toshitsugu NAKAO, Makoto NAGASE, et al. · Journal of Nuclear Science and Technology · 47
Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (I) Air-Water Tests for 1/15-Scale Model of a PWR Hot Leg
2010 · Noritoshi MINAMI, Daisuke NISHIWAKI, et al. · Journal of Nuclear Science and Technology · 45
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Influence of Local Flow Field on Flow Accelerated Corrosion Downstream from an Orifice
2012 · Yoichi UTANOHARA, Yukinori NAGAYA, et al. · Journal of Power and Energy Systems · 44
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Influence of flow velocity and temperature on flow accelerated corrosion rate at an elbow pipe
2018 · Y. Utanohara, M. Murase · Nuclear Engineering and Design · 42
Void Fraction in a Four by Four Rod Bundle under a Stagnant Condition
2010 · Akihiro KAMEI, Shigeo HOSOKAWA, et al. · Journal of Power and Energy Systems · 35
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Countercurrent Flow Limitation at the Junction between the Surge Line and the Pressurizer of a PWR
2012 · Taiga Doi, Takashi Futatsugi, et al. · Science and Technology of Nuclear Installations · 28
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Drift-Flux Parameters for Upward Gas Flow in Stagnant Liquid
1987 · Yoshiyuki KATAOKA, Hiroaki SUZUKI, et al. · Journal of Nuclear Science and Technology · 28
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Effects of fluid properties on CCFL characteristics at a vertical pipe lower end
2015 · Takayoshi Kusunoki, Michio Murase, et al. · Journal of Nuclear Science and Technology · 25
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Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling (II) Numerical Simulation of 1/15-Scale Air-Water Tests
2010 · Noritoshi Minami, Michio MURASE, et al. · Journal of Nuclear Science and Technology · 24
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Conceptual Design and Thermal-Hydraulic Characteristics of Natural Circulation Boiling Water Reactors
1988 · Yoshiyuki Kataoka, Hiroaki Suzuki, et al. · Nuclear Technology · 21
Countercurrent Gas-Liquid Flow in Boiling Channels
1986 · Michio MURASE, Hiroaki SUZUKI, et al. · Journal of Nuclear Science and Technology · 21
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Correlation between Flow Accelerated Corrosion and Wall Shear Stress Downstream from an Orifice
2013 · Yoichi UTANOHARA, Yukinori NAGAYA, et al. · Journal of Power and Energy Systems · 20
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Numerical simulation using CFD software of countercurrent gas–liquid flow in a PWR hot leg under reflux condensation
2011 · Yoichi Utanohara, Ikuo Kinoshita, et al. · Nuclear Engineering and Design · 20
Experimental study on interfacial and wall friction factors under counter-current flow limitation in vertical pipes with sharp-edged lower ends
2019 · Raito Goda, Kosuke Hayashi, et al. · Nuclear Engineering and Design · 19
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Numerical Simulation of Countercurrent Gas-Liquid Flow in a PWR Hot Leg under Reflux Cooling
2010 · Ikuo KINOSHITA, Michio MURASE, et al. · Journal of Nuclear Science and Technology · 18
Condensation experiments for counter-current flow limitation in an inverted U-tube
2015 · Takayoshi Kusunoki, Takahiro Nozue, et al. · Journal of Nuclear Science and Technology · 17
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Countercurrent Air-Water Flow in a Scale-Down Model of a Pressurizer Surge Line
2012 · Takashi Futatsugi, Chihiro Yanagi, et al. · Science and Technology of Nuclear Installations · 17
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Experimental Study on Heat Removal Characteristics for Water Wall Type Passive Containment Cooling System
1994 · Yoshiyuki KATAOKA, Tadashi FUJII, et al. · Journal of Nuclear Science and Technology · 17
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Comparison of Countercurrent Flow Limitation Experiments Performed in Two Different Models of the Hot Leg of a Pressurized Water Reactor With Rectangular Cross Section
2010 · Christophe Vallée, Tobias Seidel, et al. · Journal of Engineering for Gas Turbines and Power · 15
Evaluation of Reflux Condensation Heat Transfer of Steam-Air Mixtures under Gas-Liquid Countercurrent Flow in a Vertical Tube
2005 · Takashi NAGAE, Michio MURASE, et al. · Journal of Nuclear Science and Technology · 15
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Works count: 229
Citation count: 1,490
H-index: 19
I10-index: 46
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