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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.


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

Development of Moisture Separator With High Performance of Steam Generator

Kenji Nishida; Toshiyuki Mizutani; Tadahiko Suzuta; Yoshiyuki Kondo; Yasuhiko Hirao

A steam generator of PWR plant has moisture separators with function to separate water from two-phase flow of water and steam. Recently, corresponding to the request for power uprating of current and/or future plants with large thermal capacity, development of high performance moisture separator, which can deal with the increasing steam flow rate, has been required. Therefore, MHI has developed the moisture separator with high performance (J Model) by conducting a verification test under actual plant operating conditions (high pressure and high temperature). The developed separator’s main features are: swirl vane hub with a small diameter, horizontal slits at riser barrel, and slots with lips at the downcomer barrel. Based on the combination of the high pressure test results and thermal hydraulic analyses, value of moisture carry over (MCO) at SG outlet was evaluated. The evaluation resulted in the MCO value of less than 0.01% (our target value: 0.1%).Copyright


Archive | 2007

Steam-water separator

Yoshiyuki Kondo; Tadahiko Suzuta; Toshiyuki Mizutani; Yasuhiko Hirao


Archive | 2002

Moisture separator, and vapor generator

Tatsuo Ishiguro; Yoshiyuki Kondo; Yasuhiko Hirao; Hiroshi Hirano; Toshiyuki Mizutani; Tomoyuki Inoue; Kaori Nagai; Junichiro Kodama


Journal of Nuclear Science and Technology | 2012

Development of Steam Separator Performance Analysis Code and Its Validation, (III)

Hiroyasu Mochizuki; Yasuhiko Hirao


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


Journal of Nuclear Science and Technology | 1994

DEVELOPMENT OF STEAM SEPARATOR PERFORMANCE ANALYSIS CODE AND ITS VALIDATION. III: VALIDATION OF CODE FOR CARRYOVER

Hiroyasu Mochizuki; Yasuhiko Hirao


Journal of Nuclear Science and Technology | 2012

Development of ATR Type Steam Separator Performance Analysis Code and Its Validation, (I)

Hiroyasu Mochizuki; Yasuhiko Hirao


The proceedings of the JSME annual meeting | 2003

Development of Moisture Separator with High Performance of Steam Generator

Kenji Nishida; Toshiyuki Mizutani; Tadahiko Suzuta; Yoshiyuki Kondoh; Yasuhiko Hirao


The Proceedings of the National Symposium on Power and Energy Systems | 2002

Development of Integrated Modular Water Reactor : Standalone Safety System

Tadahiko Suzuta; Yoshiaki Makihara; Takashi Naito; Koichi Tanimoto; Jyunji Ogata; Yasuhiko Hirao; Kazuhiko Yamamoto; Akimi Serizawa; Tetsuo Matsumura

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Tadahiko Suzuta

Mitsubishi Heavy Industries

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Toshiyuki Mizutani

Mitsubishi Heavy Industries

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Ayao Tsuge

Mitsubishi Heavy Industries

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Masami Taniguchi

Mitsubishi Heavy Industries

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Yoshiaki Aoki

Mitsubishi Heavy Industries

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Yoshiyuki Kondo

Mitsubishi Heavy Industries

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Kenji Nishida

Mitsubishi Heavy Industries

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Hiroshi Hirano

Mitsubishi Heavy Industries

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