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Journal of Nuclear Science and Technology | 1999

Development of Simplified Wave-type Vane in BWR Steam Dryer and Assessment of Vane Droplet Removal Characteristics

Toshitsugu Nakao; Makoto Nagase; Goro Aoyama; Michio Murase

Air-water experiments were performed for the BWR steam dryer in order to elucidate droplet removal characteristics of the vane. Based on the results, a simplified vane was developed and its droplet removal characteristics were confirmed by air-water experiments using a whole dryer model. Phase-Doppler anemometer was used to measure droplet diameter distributions. In the experiments of the current vane with four-wave stages and 120° bend angle, almost all of the droplets were found to be trapped in the first and second vane stages. For the air velocity of 3.1 m/s, 90% of the inlet droplets were trapped there and 4% were trapped in the third and fourth stages, resulting in 6% being carried over. Sauter mean diameters at the exit were 6 and 5μm while at the inlet they were 71 and 64μm for the respective air velocities of 1 and 3 m/s. Based on the Weber number evaluation, the possible mechanism for the fine droplet generation was considered to be the breakup of droplets due to impingement on the liquid film f...


Journal of Nuclear Science and Technology | 2014

Preliminary test of an ultrasonic liquid film sensor for high-temperature steam–water two-phase flow experiments

Goro Aoyama; Takuji Nagayoshi; Atsushi Baba

A prototype liquid film sensor for high-temperature steam–water experiments has been developed. The sensor shape simulates a boiling water reactor (BWR) fuel rod. The pulse-echo method can be utilized to measure the thickness of the liquid film covering the sensor surface. A piezoelectric element is soldered onto the inside of the sensor casing which consists of two curved casing pieces. After the piezoelectric element is attached, the two casing pieces are laser welded together. It is confirmed that the temperature rise at the time of the laser welding does not influence soldering of the piezoelectric element. The pressure proof test shows that the sensor can be used at a high-pressure condition of 7 MPa. Simple air–water experiments are done at atmospheric pressure to confirm the liquid film thickness can be measured with the sensor. The fluctuation of the liquid film thickness is satisfactorily captured with the sensor. The minimum and maximum thicknesses are 0.084 and 0.180 mm, respectively. The amplitude of the waveform at 286 °C is predicted by the calculation based on the acoustic impedance. It is expected that the sensor is able to measure the liquid film thickness even at BWR operating conditions.


Journal of Nuclear Science and Technology | 2016

Application results of a prototype ultrasonic liquid film sensor to a 7 MPa steam–water two-phase flow experiment

Goro Aoyama; Kiyoshi Fujimoto; Kenichi Katono; Takuji Nagayoshi; Atsushi Baba; Kenichi Yasuda

A prototype ultrasonic liquid film sensor was applied to a high-temperature steam–water two-phase flow experiment. The liquid film sensor was vertically installed in a loop which was connected to HUSTLE, a multi-purpose steam source test facility. The hydraulic diameter of the measurement section was 9.4 mm. The output waveforms of the sensor were acquired with a digital oscilloscope. The fluid temperature and system pressure were kept at 288 °C and 7.2 MPa, respectively, during the experiment. The pulse-echo method was used to calculate the liquid film thickness. The cross-correlation calculation was utilized to determine the time difference between the pulse reflected at the sensor surface and the pulse reflected at the liquid film surface. The time-averaged liquid film thicknesses were less than 0.055 mm in the annular flow condition. The increase of the time-averaged thickness was small with the change of the gas momentum flux. The film thicknesses measured with the sensor were compared with the past experimental results; the former were smaller than one-fourth of the thickness estimated as the mean film thickness. The comparison results suggested that the continuous liquid sublayer thickness was measured with the liquid film sensor.


Journal of Nuclear Science and Technology | 2000

A high temperature sodium test facility for development of passive safety devices in FBRs

Yoshinori Saito; Kazuo Takahashi; Goro Aoyama; Tadashi Goto; Kazumasa Ozawa; Hiromi Tokoi

In a large fast breeder reactor (FBR), passive safety devices are able to introduce a negative reactivity effect passively to prevent a core disruptive accident during an anticipated transient without scram. A high temperature sodium test facility was developed to investigate and develop the passive safety devices. This facility can be used for liquid sodium tests at a maximum pressure of 1 MPa and 700° C or for sodium boiling tests up to 1,000°C. Preliminary tests using a gas expansion module unit were carried out with the core conditions of a large FBR. Experimental results were obtained as follows. (1) The gas expanding process is similar to an isothermal one. (2) The gas expansion speed increases gradually due to sodium flow resistance and inertia. (3) Since forced convection by the gas expansion promotes heat transfer, the heat transfer increases rapidly at the start of expansion. (4) The above experimental results are used to propose an empirical correlation.


Journal of Nuclear Science and Technology | 1988

Sodium Tests of Head-Flow Characteristics for Prototype Annular Electromagnetic Flow Coupler

Takashi Ikeda; Goro Aoyama; Tadashi Gotou; Ryuhei Kawabe; Takao Koyama

A prototype annular electromagnetic flow coupler was tested with high temperature sodium and it worked successfully, verifying the operational principle. The pump head-flow characteristics of the coupler were first clarified from an analysis of its equivalent electric circuit. The pump head and the generator pressure drop decrease linearly with the pump flow rate under the conditions of constant generator flow rate and external magnetic flux density. The gradients of the linear changes are given by ratios of equivalent resistances in the electrical analog, and are independent of the generator flow rate, if the magnetic flux density is kept constant. Sodium tests of the prototype confirmed the above results when the Hartmann number of the test conditions is larger than 170. Both ratios of the differential pressures and the volumetric flow rate between pump and generator ducts exceed 50% while the wall loss of around 40% appears at peak efficiency due to the lack of electrical insulation and the relatively ...


Journal of Nuclear Science and Technology | 1998

Droplet Behavior Analyses in the BWR Dryer and Separator

Toshitsugu Nakao; Yoshinori Saito; Hisashi Souma; Terufumi Kawasaki; Goro Aoyama


Journal of Nuclear Science and Technology | 1994

Analysis of Droplet Behavior in BWR Separator

Yoshinori Saito; Goro Aoyama; Hisashi Souma; Toshitsugu Nakao; Isao Sumida


Archive | 1988

Circular electromagnetic flow coupler

Goro Aoyama; Ryuhei Kawabe; Takashi Ikeda; Tadashi Goto


Archive | 1991

FAST BREEDER REACTOR AND PUMP EQUIPMENT USED THEREFOR

Goro Aoyama; Tadashi Goto; Yoshihiko Sato; 吉彦 佐藤; 忠 後藤; 吾朗 青山


Journal of Nuclear Science and Technology | 1992

Structural Effects on Electromagnetic Flow Coupler Performance

Goro Aoyama; Norikatsu Yokota; Masao Mine; Takashi Watanabe; Tadasu Takuma; Kiyoshi Takenaka

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