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Nuclear Engineering and Design | 1990

An experimental study on drift flux parameters for two-phase flow in vertical round tubes

Kouhei Kawanishi; Yasuhiko Hirao; Ayao Tsuge

Correlations which can correctly express the velocity difference between steam and water of two-phase flow are required for accurate predictions of the thermal-hydraulic transient behaviour for a pressurized water reactor (PWR) power plant during a small break loss-of-coolant accident (LOCA). A drift flux model is one of the typical models which describes the relative velocity between the two phases. A number of empirical expressions of the parameters for the drift flux model have been proposed based on experiments. It is necessary to confirm whether those formulas are applicable to the simulation of two-phase flow behaviour in a large scale apparatus such as the actual PWR plant. In this study, the experiments of cocurrent and counter-current steam-water two-phase flow using a large scale apparatus with 0.1023 m diameter tubes, and small scale apparatus with 0.0197 m diameter tubes were carried out. This paper presents the tube diameter effects on the drift flux parameters (Co = distribution parameter and Vgj = drift velocity). In addition, new empirical correlations of the drift flux parameters for the two-phase flow in large diameter tubes are proposed. A root mean square error of the predicted void fraction is 16.8% compared with 1353 experimental data.


Nuclear Engineering and Design | 1990

Small break loch experiments and verification of CANAC-II code

Kouhei Kawanishi; Ayao Tsuge; K. Kuwabara; O. Ukai; Nobuo Nakamori

Abstract Scaled experiments on small break, loss-of-coolant accidents have been conducted. The tests simulated loss-of-coolant accidents (LOCAs) resulting from a 0.53% and a 0.13% communicative break in the cold leg and the pressurizer power operated relief valve (PORV). The thermal-hydraulic behavior such as natural circulation and reflux condensation cooling during a small break LOCA has been investigated. A new computer program CANAC-II (a Computer Analysis Program of Natural Circulation for multi-loop systems) has been developed and verified based upon comprehensive tests. A drift flux model was applied for two-phase flow in CANAC-II. It also has a shorter computer running time than the real time.


Journal of Fluids and Structures | 1995

Study on the Vibrational Characteristics of a Tube Array Caused by Two-Phase Flow. Part II: Fluidelastic Vibration

Tomomichi Nakamura; K. Fujita; K. Kawanishi; N. Yamaguchi; Ayao Tsuge


Journal of Fluids and Structures | 1995

Study on the Vibrational Characteristics of a Tube Array Caused by Two-Phase Flow. Part I: Random Vibration

Tomomichi Nakamura; K. Fujita; K. Kawanishi; N. Yamaguchi; Ayao Tsuge


Jsme International Journal Series B-fluids and Thermal Engineering | 1993

Two-Phase Cross-Flow-Induced Vibration of Tube Arrays. (Brief Review of Previous Studies and Summary of Design Methods).

Tomomichi Nakamura; Katsuhisa Fujita; Ayao Tsuge


Journal of Nuclear Science and Technology | 1990

Experimental Study on PORV Break LOCA in PWR Plants

Kouhei Kawanishi; Nobuo Nakamori; Ayao Tsuge; Kenji Kodama; Tamio Kohriyama; Hiroichi Nagumo


Jsme International Journal Series B-fluids and Thermal Engineering | 1993

Development of Thermal-hydraulic Computer Code for Steam Generator

Yasuhiko Hirao; Nobuo Nakamori; Osamu Ukai; Kohei Kawanishi; Ayao Tsuge; Takashi Ueno; Takaya Kusakabe


Jsme International Journal Series B-fluids and Thermal Engineering | 2000

Numerical Simulation of Two-Phase Boiling Flows and Prediction of DNB under PWR Conditions with a Multidimensional Two-Fluid Model.

Yan F. Rao; Keiichi Hori; Ayao Tsuge


Archive | 1991

Waste heat recovery apparatus for nuclear power plant

Akihiro Kawada; Kohei Kawanishi; Nobuo Nakamori; Tamotsu Sano; Ayao Tsuge


Proceedings of the ... JSME-KSME Thermal Engineering Conference | 2000

A303 Numerical Simulation of Two-Phase Boiling Flows and Prediction of DNB under PWR Conditions with a Multidimensional Two-Fluid Model(Subcooled boiling)

Yan F. Rao; Keiichi Hori; Ayao Tsuge

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Nobuo Nakamori

Mitsubishi Heavy Industries

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Yasuhiko Hirao

Mitsubishi Heavy Industries

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Kouhei Kawanishi

Mitsubishi Heavy Industries

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Tomomichi Nakamura

Mitsubishi Heavy Industries

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K. Fujita

Mitsubishi Heavy Industries

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K. Kawanishi

Mitsubishi Heavy Industries

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N. Yamaguchi

Mitsubishi Heavy Industries

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