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Ikuo Kinoshita
Observed names:
I. Kinoshita,
Ikuo KINOSHITA,
Kinoshita, Ikuo
Institution:
Institute of Nuclear Safety System, Inc. (Japan)
Observed institutions:
Hôpital de l'Enfant-Jésus,
Université Laval,
Institute of Nuclear Safety System, Inc. (Japan),
Kobe University
ORCID:
0000-0001-5915-1557
Observed ORCID:
0000-0001-5915-1557
OpenAlex ID:
A5063420183
Drift-flux correlation for rod bundle geometries
2014
·
Collin Clark
, Matthew Griffiths
, et al.
·
International Journal of Heat and Fluid Flow
·
70
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
Correlation for countercurrent flow limitation in a PWR hot leg
2012
·
Michio Murase
, Akio Tomiyama
, et al.
·
Journal of Nuclear Science and Technology
·
57
PDF
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
PDF
Phenomena identification and ranking table for thermal-hydraulic phenomena during a small-break LOCA with loss of high pressure injection
2014
·
M.J. Griffiths
, J.P. Schlegel
, et al.
·
Progress in Nuclear Energy
·
32
Experimental study of void fraction in an 8×8 rod bundle at low pressure and low liquid flow conditions
2014
·
Collin Clark
, Matthew Griffiths
, et al.
·
International Journal of Multiphase Flow
·
29
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
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
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
Uncertainty evaluation of the Chexal–Lellouche correlation for void fraction in rod bundles
2014
·
M.J. Griffiths
, J.P. Schlegel
, et al.
·
Progress in Nuclear Energy
·
15
Improved drift-flux correlation to enhance the prediction of void fraction in nuclear reactor fuel bundles at low flow and elevated pressure conditions
2019
·
Ikuo Kinoshita
, Joshua P. Schlegel
, et al.
·
Journal of Nuclear Science and Technology
·
13
Numerical Simulation of Size Effects on Countercurrent Flow Limitation in PWR Hot Leg Models
2012
·
I. Kinoshita
, M. Murase
, et al.
·
Science and Technology of Nuclear Installations
·
10
PDF
Effects of Liquid Properties on CCFL in a Scaled-Down Model of a PWR Hot Leg
2011
·
Ikuo KINOSHITA
, Toshifumi NRIAI
, et al.
·
Journal of Power and Energy Systems
·
10
PDF
Numerical Calculations on Countercurrent Air-Water Flow in Small-Scale Models of a PWR Hot Leg Using a VOF Model
2009
·
Michio Murase
, Yoichi Utanohara
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
·
10
Numerical simulations for steam–water CCFL tests using the 1/3 scale rectangular channel simulating a PWR hot leg
2011
·
Yoichi Utanohara
, Ikuo Kinoshita
, et al.
·
Nuclear Engineering and Design
·
9
Letters to te editor
1995
·
Yann Péréon
, Jean‐Marc Bernard
, et al.
·
Muscle & Nerve
·
9
Effects of Shape and Size on Countercurrent Flow Limitation in Flow Channels Simulating a PWR Hot Leg
2014
·
Ikuo Kinoshita
, Michio Murase
, et al.
·
Nuclear Technology
·
8
VOF Simulations of Countercurrent Gas-Liquid Flow in a PWR Hot Leg
2012
·
Michio Murase
, Yoichi Utanohara
, et al.
·
The Journal of Computational Multiphase Flows
·
7
PDF
VOF Calculations of Countercurrent Gas-Liquid Flow in a PWR Hot Leg
2012
·
M. Murase
, A. Tomiyama
, et al.
·
Science and Technology of Nuclear Installations
·
7
PDF
Countercurrent Gas-Liquid Flow in a Rectangular Channel Simulating a PWR Hot Leg (3)
2010
·
Ikuo KINOSHITA
, Michio MURASE
, et al.
·
JAPANESE JOURNAL OF MULTIPHASE FLOW
·
7
PDF
Validation of thermal–hydraulic system code improved by advanced drift-flux correlation using bundle data at moderate pressure conditions
2022
·
I. Kinoshita
, T. Hibiki
·
Nuclear Engineering and Design
·
5
PDF
Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows
2015
·
Michio Murase
, Ikuo Kinoshita
, et al.
·
Journal of Nuclear Engineering and Radiation Science
·
5
Correlation of interfacial friction for countercurrent gas-liquid flows in nearly horizontal pipes
2017
·
Michio Murase
, Yasunori Yamamoto
, et al.
·
Nuclear Engineering and Design
·
4
Prediction Accuracy of One-dimensional Computation for Countercurrent Flow Limitation in Horizontal Pipes
2016
·
Michio MURASE
, Ikuo KINOSHITA
, et al.
·
JAPANESE JOURNAL OF MULTIPHASE FLOW
·
4
PDF
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Works count:
66
Citation count:
553
H-index:
12
I10-index:
15
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