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Featured researches published by Hiroyuki Miyakoshi.


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.


12th International Conference on Nuclear Engineering, Volume 3 | 2004

Study on Mixing Due to Transversal Flow in a Fuel Subassembly of Fast Reactor: Sodium Experiment Using a 37-Pin Subassembly Model

Hideki Kamide; Hiroyuki Miyakoshi; Nobuhiro Kawamata; Hiroyuki Ohshima

Estimation of the highest temperature in a fuel subassembly is needed for safety and reliable operation of fast reactors. Cross flow has a significant role for mixing phenomena in the subassembly. Especially, the cross flow will be enhanced in a deformed pin bundle of high burnup core. Such mixing due to the cross flow was investigated. Sodium experiments were carried out using a wire wrapped 37-pin subassembly model. In order to see a cross flow in a simple and clear geometry as an element of mixing phenomena, a blockage was installed in the subassembly. Mixing due to the cross flow was found in the experiment. The subchannel analysis code, ASFRE, was applied to the experimental analyses. Measured axial and transverse temperature distributions in the subassembly were correlated with the cross flow and the wire spacer. The calculated temperature profiles were in good agreement with the experimental results. ASFRE simulated the influence of the wire spacer also. Database for the mixing phenomena with the cross flow was obtained.Copyright


Jsme International Journal Series B-fluids and Thermal Engineering | 2002

Evaluation method for core thermohydraulics during natural circulation in fast reactors: (Numerical predictions of inter-wrapper flow)

Hideki Kamide; Kazuyoshi Nagasawa; Nobuyuki Kimura; Hiroyuki Miyakoshi


Transactions of the Japan Society of Mechanical Engineers. B | 2010

Experimental Studies of Natural Circulation Decay Heat Removal in Japan Sodium Cooled Fast Reactor (JSFR)( The 14th National Symposium on Power and Energy System)

Hideki Kamide; Hiroyuki Miyakoshi; Osamu Watanabe; Yuzuru Eguchi; Tomonari Koga


Transactions of the Japan Society of Mechanical Engineers. B | 2010

Experimental Study of Gas Entrainment Phenomena in Sodium Cooled Fast Reactor by 1/1.8 Scale Partial Model( The 14th National Symposium on Power and Energy System)

Toshiki Ezure; Nobuyuki Kimura; Hiroyuki Miyakoshi; Hideki Kamide


The Proceedings of the National Symposium on Power and Energy Systems | 2009

E203 Experimental Studies of Natural Circulation Decay Heat Removal in Japan Sodium Cooled Fast Reactor (JSFR)

Hideki Kamide; Hiroyuki Miyakoshi; Osamu Watanabe; Yuzuru Eguchi; Tomonari Koga


The Proceedings of the National Symposium on Power and Energy Systems | 2009

E201 Experimental Study of Gas Entrainment Phenomena in Sodium Cooled Fast Reactor by 1/1.8 Scale Partial Model

Toshiki Ezure; Nobuyuki Kimura; Hiroyuki Miyakoshi; Hideki Kamide


The proceedings of the JSME annual meeting | 2003

Study on High Cycle Thermal Fatigue of FBR plants(3) Comparison of Temperature Fluctuation Characteristics between Water and Sodium

Nobuyuki Kimura; Hiroyuki Miyakoshi; Minoru Igarashi; Hideki Kamide


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2003

ICONE11-36362 STUDY ON THERMAL-HYDRAULICS IN A POROUS BLOCKAGE IN A FUEL SUBASSEMBLY OF LMFBR

Masaaki Tanaka; Hideki Kamide; Hiroyuki Miyakoshi; Jun Kobayashi


Proceedings of the ... ASME/JSME Thermal Engineering Joint Conference | 2003

TED-AJ03-159 EXPERIMENTAL STUDY ON THERMAL STRIPING PHENOMENA FOR A FAST REACTOR : TRANSFER CHARACTERISTICS OF TEMPERATURE FLUCTUATION FROM FLUID TO STRUCTURE

Nobuyuki Kimura; Hiroyuki Miyakoshi; Minoru Igarashi; Hideki Kamide

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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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Minoru Igarashi

Japan Nuclear Cycle Development Institute

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Toshiki Ezure

Japan Atomic Energy Agency

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Tomonari Koga

Central Research Institute of Electric Power Industry

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Hiroyuki Ohshima

Japan Nuclear Cycle Development Institute

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Jun Kobayashi

Japan Atomic Energy Agency

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Masaaki Tanaka

Japan Atomic Energy Agency

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