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Dive into the research topics where Hisato Watakabe is active.

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Featured researches published by Hisato Watakabe.


Journal of Fluids Engineering-transactions of The Asme | 2006

Resistance and Fluctuating Pressures of a Large Elbow in High Reynolds Numbers

Tadashi Shiraishi; Hisato Watakabe; Hiromi Sago; Mamoru Konomura; Akira Yamaguchi; Tadashi Fujii

For the Japan Atomic Energy Agency sodium-cooled fast reactor, an experimental study on the fluctuating pressure of the hot legs was carried out with tests in a 1/3-scale model. The total resistance coefficient is consistent with published data, and, additionally, our research has given data up to the Reynolds number of 8.0×106. The flow visualization and velocity measurement confirmed the independence of the flow on the Reynolds number. Pressures on the pipe wall were statistically examined to predict the characteristics of fluctuating pressures of the hot legs. It reveals that generation of fluctuating pressure is dominant on the boundary of flow separation and reattachment.


Nuclear Technology | 1994

Characteristics of the flow-controlled accumulator

Tadashi Shiraishi; Hisato Watakabe; Nobuo Nakamori; Kozo Tabuchi; Yoji Takayama; Takayoshi Sugizaki

Mitsubishi is developing a new type of accumulator incorporating the technology of fluidics as one of the seeds for the improved safety of the newly constructed pressurized water reactor plants. This accumulator employs a vortex flow control device, called a vortex damper, as a fluidic device to simplify the safety systems. A fundamental experimental study with a one-fifth scale model and confirmation tests with a one-third scale model to develop the vortex damper have been carried out, and satisfactory results have been achieved. The results of the confirmation tests under the prototype pressure conditions agree well with the basic tests. The flow rate ratio can be 5 to 6. The pressure loss coefficient in the large flow rate period is 8. A cavitation factor is the main parameter of the flow rate coefficient.


ASME 2005 Pressure Vessels and Piping Conference | 2005

Flow-Induced Vibration of a Large-Diameter Elbow Piping Based on Random Force Measurement Caused by Conveying Fluid: Visualization Test Results

Tomomichi Nakamura; Tadashi Shiraishi; Yoshihide Ishitani; Hisato Watakabe; Hiromi Sago; Tadashi Fujii; Akira Yamaguchi; Mamoru Konomura

A 1/3 scale flow-induced vibration test facility that simulates the hot-leg piping of the JNC sodium-cooled fast reactor (JSFR) is used to investigate the pressure fluctuations of the pipe, where the high velocity fluid flows inside the piping. By the measurement of the pressure drop in the elbow piping while changing the Reynolds number, the similarity law of this model is confirmed. To evaluate the flow-induced vibrations for the hot-leg and cold-leg pipes, the random force distributions along the pipe and their correlations are measured with pressure sensors in a water loop. It is found that a flow velocity-dependent periodic phenomenon in the rear region of the elbow, and the maximum flow-induced random vibration force in the pipe are observed in the region of flow separation downstream the elbow. Finally, a design method is proposed with power spectral densities of the pressure fluctuations classified into four sections, correlation lengths in the axial direction divided into three sections, and with correlation lengths in the tangential direction into four sections.Copyright


Journal of Fluid Science and Technology | 2009

Pressure Fluctuation Characteristics of the Short-Radius Elbow Pipe for FBR in the Postcritical Reynolds Regime

Tadashi Shiraishi; Hisato Watakabe; Hiromi Sago; Hidemasa Yamano


Nuclear Engineering and Design | 2012

Development of the advanced accumulator for the pressurized water reactor

Tadashi Shiraishi; Hisato Watakabe


Archive | 2009

STEAM GENERATOR AND METHOD OF ADJUSTING FLOW RESISTANCE OF COOLING WATER IN STEAM GENERATOR

Hisato Watakabe; Tomoyuki Inoue


Archive | 2005

Steam generator, and flow resistance adjusting method for cooling water in steam generator

Tomoyuki Inoue; Hisato Watakabe; 智之 井上; 壽人 渡壁


Transactions of the Japan Society of Mechanical Engineers. B | 2012

Flow Pattern and Pressure Fluctuation Characteristics on the 1/3 Scale Hot-Leg Piping Experiments of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor

Hiromi Sago; Tadashi Shiraishi; Hisato Watakabe; Yang Xu; Kousuke Aizawa; Hidemasa Yamano


The Proceedings of Mechanical Engineering Congress, Japan | 2011

S054092 Evaluation for Flow-Induced Vibration of a Primary Circuit Hot-Leg Piping in a Sodium-Cooled Fast Reactor (2) Flow Pattern and Pressure Fluctuation Characteristics on the 1/3 Scale Hot-leg Piping Experiments

Hiromi Sago; Tadashi Shiraishi; Hisato Watakabe; Yang Xu; Kousuke Aizawa; Hidemasa Yamano


Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE | 2011

ICONE19-43712 STUDY ON FLOW INDUCED VIBRATION EVALUATION FOR A LARGE SCALE JSFR PIPING : (3) PRESSURE FLUCTUATION CHARACTERISTICS IN 1/3 SCALE HOT-LEG PIPING EXPERIMENTS UNDER DEFLECTED INFLOW CONDITIONS DUE TO UIS STRUCTURES

Hiromi Sago; Tadashi Shiraishi; Hisato Watakabe; Yang Xu; Kousuke Aizawa; Hidemasa Yamano

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Tadashi Shiraishi

Mitsubishi Heavy Industries

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Hiromi Sago

Mitsubishi Heavy Industries

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Mamoru Konomura

Japan Nuclear Cycle Development Institute

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Tadashi Fujii

Japan Nuclear Cycle Development Institute

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Akira Yamaguchi

Japan Nuclear Cycle Development Institute

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Hidemasa Yamano

Japan Atomic Energy Agency

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Tomomichi Nakamura

Mitsubishi Heavy Industries

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Yoshihide Ishitani

Mitsubishi Heavy Industries

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Kousuke Aizawa

Japan Atomic Energy Agency

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Tomoyuki Inoue

Mitsubishi Heavy Industries

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