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Dive into the research topics where Toshiki Ezure is active.

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Featured researches published by Toshiki Ezure.


Journal of Nuclear Science and Technology | 2008

Experimental Study on Gas Entrainment at Free Surface in Reactor Vessel of a Compact Sodium-Cooled Fast Reactor

Nobuyuki Kimura; Toshiki Ezure; Akira Tobita; Hideki Kamide

An innovative sodium-cooled fast reactor has been investigated as part of the fast reactor cycle technology development (FaCT) project. In the reactor, a compact reactor vessel (R/V) with increased sodium flow velocity was designedto reduce the construction cost. One of the thermal hydraulic problems associated with this design is gas entrainment at the free surface in the R/V. Horizontal plates are set below the free surface in order to prevent the gas entrainment. A water experiment was performed using a partial model built to 1/1.8 scale. The objective was to investigate the occurrence of gas entrainment under certain conditions and the mechanism of the gas entrainment. It was found that there were two types of gas entrainment phenomenon, and the conditions for their occurrence were far different from the rated condition in the reactor. One type of gas entrainment occurred at the wake region of flow around the cold leg pipe created due to the larger horizontal velocity in the R/V. The other type of gas entrainment occurred at the region between the hot leg pipe and the R/V wall when the coolant level was low and the downward velocity was large. The mechanisms of the gas entrainment at the two regions were clarified by the detailed measurement of transient flow velocity field.


Heat Transfer Engineering | 2008

Transient Behavior of Gas Entrainment Caused by Surface Vortex

Toshiki Ezure; Nobuyuki Kimura; Kenji Hayashi; Hideki Kamide

A compact sodium-cooled reactor is an important candidate as a fast breeder reactor (FBR) and has been investigated in the feasibility study of FBR cycle. Due to the compact sizing of the reactor vessel, gas entrainment at the free surface of sodium coolant becomes one of the significant issues for reactor design, and it is required to clarify the criterion of gas entrainment at free surface and the tolerance. In the present study, some visualization experiments were performed in a water-air system focusing on the gas entrainment due to surface vortex and its transient phenomena. Influences of horizontal velocity were clarified by the visualization. The gas entrainment due to the surface vortex occurs intermittently. Time trends of circulation and length of gas core for the intermittent surface vortices were measured by the particle image velocimetry and visualization. It was found that the gas core length extends with time delay to the increase of circulation around the vortex.


Journal of Engineering for Gas Turbines and Power-transactions of The Asme | 2010

Experimental Study on Gas Entrainment Due to Nonstationary Vortex in a Sodium Cooled Fast Reactor—Comparison of Onset Conditions Between Sodium and Water

Nobuyuki Kimura; Toshiki Ezure; Hiroyuki Miyakoshi; Hideki Kamide; Takeshi Fukuda

An innovative sodium cooled fast reactor has been investigated as part of the fast reactor cycle technology development project. In the reactor, a compact reactor vessel (R/V) with increased sodium flow velocity was designed to reduce the construction cost. One of the thermal hydraulic problems in this design is gas entrainment at the free surface in the R/V. In most of past studies, water experiments were performed to investigate the gas entrainment in the reactor. It is necessary to evaluate an influence of fluid physical property on the gas entrainment phenomena. In this study, sodium experiments were carried out to clarify the onset criteria of the gas entrainment due to a free surface vortex. Water experiments using a test section in which geometry is the same as that in the sodium tests were also performed. The gas entrainment in water slightly tended to take place in comparison with that in sodium under low velocity conditions. Overall, the onset condition map on the lateral and downward flow velocities in the sodium and water experiments were in good agreement.


Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance | 2009

Experimental Study on Gas Entrainment Due to Non-Stationary Vortex in a Sodium Cooled Fast Reactor: Comparison of Onset Conditions Between Sodium and Water

Nobuyuki Kimura; Toshiki Ezure; Hiroyuki Miyakoshi; Hideki Kamide; Takeshi Fukuda

An innovative sodium cooled fast reactor has been investigated as part of the fast reactor cycle technology development (FaCT) project. In the reactor, a compact reactor vessel (R/V) with increased sodium flow velocity was designed to reduce the construction cost. One of the thermal hydraulic problems in this design is gas entrainment at the free surface in the R/V. In most of past studies, water experiments were performed to investigate the gas entrainment in the reactor. It is necessary to evaluate an influence of fluid physical property on the gas entrainment phenomena. In this study, sodium experiments were carried out to clarify the onset criteria of the gas entrainment due to a free surface vortex. Water experiments using a test section in which geometry is the same as that in the sodium tests were also performed. The gas entrainment in water slightly tended to take place in comparison with that in sodium under low velocity conditions. Overall onset condition map on lateral and downward flow velocities in the sodium and water experiments were in good agreement.Copyright


Nuclear Engineering and Design | 2011

Experimental investigation on bubble characteristics entrained by surface vortex

Toshiki Ezure; Nobuyuki Kimura; Hiroyuki Miyakoshi; Hideki Kamide


Transactions of the Japan Society of Mechanical Engineers. B | 2013

Numerical Simulation of Cavitation by Sub-Surface Vortex (2nd Report, Theoretical Modeling of Unsteady Vortex Cavitation)

Kei Ito; Toshiki Ezure; Shuji Ohno; Hideki Kamide


The Proceedings of Mechanical Engineering Congress, Japan | 2017

Water Experiments on Thermal Striping around Upper Internal Structure in An Advanced Sodium cooled Fast Reactor

Jun Kobayashi; Toshiki Ezure; Masaaki Tanaka; Hideki Kamide


日本伝熱学会論文集 | 2016

Study on Behavior of Vortex Cavitation around Suction Pipes in Sodium-Cooled Fast Reactor Geometry

Toshiki Ezure; Kei Ito; Hideki Kamide; Tomoaki Kunugi


The Proceedings of Mechanical Engineering Congress, Japan | 2016

Water Experiments on Thermal Striping at Upper Internal Structure of Japan Sodium-cooled Fast Reactor

Jun Kobayashi; Toshiki Ezure; Masaaki Tanaka; Hideki Kamide


Atomic Energy Society of Japan | 2016

Study on Cavitation Due to Sub-Surface Vortex at Intake of Hot-Leg Pipe in Sodium Cooled Fast Reactor

Toshiki Ezure

Collaboration


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Hideki Kamide

Japan Atomic Energy Agency

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Nobuyuki Kimura

Japan Nuclear Cycle Development Institute

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Hiroyuki Miyakoshi

Japan Nuclear Cycle Development Institute

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Akira Tobita

Japan Atomic Energy Agency

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Masaaki Tanaka

Japan Atomic Energy Agency

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Shuji Ohno

Japan Atomic Energy Agency

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Jun Kobayashi

Washington University in St. Louis

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