• Title/Summary/Keyword: Hydraulic Nozzle

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A Study on Injection Nozzle and Internal Flow Velocity for Removing Air Bubbles inside the Sample Tanks during Hydraulic Rupture Test (수압파열시험 시 시료 탱크 내부 기포 제거를 위한 주입 노즐 및 내부 유속 연구)

  • Yeseung, Lee;Hyunseok, Yang;Woo-Chul, Jung;Dong Hoon, Lee;Man-Sik, Kong
    • Journal of the Korean Institute of Gas
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    • v.26 no.6
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    • pp.9-15
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    • 2022
  • In order to verify the durability of the high-pressure hydrogen tank in the operating pressure range, a hydraulic rupture test should be performed. However, if the bubbles generated by the initial injection process of water are attached to the inner wall of the tank and remain, a sudden pressure change of the bubbles during the rupture of the pressurized tank may cause shock and noise. Therefore, in this study, the flow velocity required to remove the bubbles remaining on the inner wall of the tank was predicted through simplified formulas, and the shape of the injection nozzle to maintain the flow velocity was determined based on the shape of the hydrogen tank for the hydrogen bus. In addition, a numerical model was developed to predict the change in flow velocity according to the inlet pressure, and an experiment was performed through a model tank to prove the validity of the prediction result. As a result of the experiment, the flow velocity near the tank wall was similar to the predicted value of the analysis model, and when the inlet pressure was 1.5 to 5.5 bar, the minimum size of the removable bubble was predicted to be about 2.2 to 4.6 mm.

Design of a Partial Inter-tube Lancing System actuated by hydraulic power for type F model Steam Generator in Nuclear Power Plant (수압구동 전열관다발 부분 삽입형 증기발생기 세정장비 설계)

  • Kim, S.T.;Jeong, T.W.
    • Proceedings of the KSME Conference
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    • 2008.11a
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    • pp.1132-1135
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    • 2008
  • The sludge grown up in steam generators of nuclear power plants shortens the life-cycle of steam generators and reduces the output of power plants. So KHNP(Korea Hydro and Nuclear Power), the only nuclear power utility in Korea, removes it periodically using a steam generator lancing system during the outage of plants for an overhaul. KEPRI(Korea Electric Power Research Institute) has developed lancing systems with high pressured water nozzle for steam generators of nuclear power plants since 2001. In this paper, the design of a partial inter-tube lancing system for model F type steam generators will be described. The system is actuated without a DC motor inner steam generators because the motors in a steam generator make a trouble from high intensity of radioactivity as a break down.

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Controller Design for a Nozzle-flapper Type Servo Valve with Electric Position Sensor

  • Istanto, Iwan;Lee, Ill-yeong;Huh, Jun-young;Lee, Hyun-cheol
    • Journal of Drive and Control
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    • v.16 no.1
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    • pp.29-35
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    • 2019
  • The control performance of hydraulic systems is basically influenced by the performance of electrohydraulic servo valve incorporated in a hydraulic control system. In this study, a control design was proposed to improve the control performance of a servo valve with a non-contact eddy current type position sensor. A mathematical model for the valve was obtained through an experimental identification process. A PI-D control together with a feedforward (FF) control was applied to the valve. To further improve the dynamic response of the servo valve, an input shaping filter (ISF) was incorporated into the valve control system. Finally, the effectiveness of the proposed control system was verified experimentally.

Development of Tip Device for Hydraulic Filling Efficiency Improvements (수압식 충전의 효율 향상을 위한 선단장치 개발에 관한 연구)

  • Yu, Sung-Kon;Kim, Tae-Heok;Shin, Dong-Chun
    • Tunnel and Underground Space
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    • v.22 no.6
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    • pp.403-411
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    • 2012
  • In recent, the using of the hydraulic filling method has increased on the underground reinforcement of the abandoned mine in Korea, however it is the lack of research on the efficient filling method. In this study, tank model tests and field tests were conducted for development of tip device for filling efficiency improvements on the hydraulic filling method. In tank model experiments, the filling efficiency was evaluated according to the form and angle of the nozzle on tip device in the same condition. Then tip device model designed by tank model tests was applied to the field experiment. As a result, the amount of filling of nozzle $90^{\circ}$ tube is increased by approximately 18% compared to the common vertical injection pipe. The angle of repose was $30.82^{\circ}$. Filling hole spacing in the field is usually designed from 5m up to 10m assumed to be $40^{\circ}$ of the angle of repose. According to the results of this study, it is possible that the filling hole spacing expands at least 10m up to 15m applied to be $30^{\circ}{\sim}35^{\circ}$ of the angle of repose. Therefore, it is expected to be economical and efficient mine filling.

Air horizontal jets into quiescent water

  • Weichao Li ;Zhaoming Meng;Jianchuang Sun;Weihua Cai ;Yandong Hou
    • Nuclear Engineering and Technology
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    • v.55 no.6
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    • pp.2011-2017
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    • 2023
  • Gas submerged jet is an outstanding thermohydraulic phenomenon in pool scrubbing of fission products during a severe nuclear accident. Experiments were performed on the hydraulic characteristics in the ranges of air mass flux 0.1-1400 kg/m2s and nozzle diameter 10-80 mm. The results showed that the dependence of inlet pressure on the mass flux follows a power law in subsonic jets and a linear law in sonic jets. The effect of nozzle submerged depth was negligible. The isolated bubbling regime, continuous bubbling regime, transition regime, and jetting regime were observed in turn, as the mass flux increased. In the bubbling regime and jetting regime, the air volume fraction distribution was approximately symmetric in space. Themelis model could capture the jet trajectory well. In the transition regime, the air volume fraction distribution loses symmetry due to the bifurcated secondary plume. The Li correlation and Themelis model showed sufficient accuracy for the prediction of jet penetration length.

Analysis on Combustion Characteristics of CRDi Single-cylinder Diesel Engine with Direct Needle-driven Piezo Injector (직접구동 피에조 인젝터의 CRDi 단기통 디젤엔진 연소 특성 분석)

  • Chung, Myungchul;Sung, Gisu;Kim, Sangmyung;Lee, Jinwook
    • Transactions of the Korean Society of Automotive Engineers
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    • v.22 no.5
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    • pp.108-115
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    • 2014
  • In this study, experimental approaching method was applied under and single-cylinder engine to research the performance of direct needle-driven piezo injector (DPI) for CR direct-injection. As key-point factor of this DPI that relies on direct-acting operating of injector needle, unlike conventional hydraulic-servo, its nozzle needle can be directly driven by piezo actuator. Thus, effect of direct-acting injection of DPI on diesel combustion and emission characteristics was investigated under common-rail single-cylinder direct-injection engine, equipped with three different driving mechanism, including indirect-acting solenoid, piezo and DPI system. As main results, it found that a direct-acting piezo injector has higher of IMEP. And it has higher heat release rate during premixed combustion and mixing controlled combustion phase due to its higher heat release, even though nitrogen oxide (NOx) formations were increased slightly.

Scoping Analyses for the Safety Injection System Configuration for Korean Next Generation Reactor

  • Bae, Kyoo-Hwan;Song, Jin-Ho;Park, Jong-Kyoon
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.395-400
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    • 1996
  • Scoping analyses for the Safety Injection System (SIS) configuration for Korean Next Generation Reactor (KNGR) are peformed in this study. The KNGR SIS consists of four mechanically separated hydraulic trains. Each hydraulic train consisting of a High Pressure Safety Injection (HPSI) pump and a Safety Injection Tank (SIT) is connected to the Direct Vessel Injection (DVI) nozzle located above the elevation of cold leg and thus injects water into the upper portion of reactor vessel annulus. Also, the KNGR is going to adopt the advanced design feature of passive fluidic device which will be installed in the discharge line of SIT to allow more effective use of borated water during the transient of large break LOCA. To determine the feasible configuration and capacity of SIT and HPSI pump with the elimination of the Low Pressure Safety Injection (LPSI) pump for KNGR, licensing design basis evaluations are performed for the limiting large break LOCA. The study shows that the DVI injection with the fluidic device SIT enhances the SIS performance by allowing more effective use of borated water for an extended period of time during the large break LOCA.

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YGN 3 & 4 Reactor Flow Model Test (영광 3, 4호기 원자로 유동 모델 시험)

  • Lee, Kye-Bock;Im, In-Young;Lee, Byung-Jin;Kuh, Jung-Eui
    • Nuclear Engineering and Technology
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    • v.23 no.3
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    • pp.340-351
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    • 1991
  • Experimental studies were conducted on a l/5.03 scale reactor flow model of the Yong-gwang Nuclear Units 3 and 4. The purpose of the flow model test was to estimate the hydraulic effect in the reactor vessel due to the relative size difference between the ABB-CE's System 80 and the YGN 3&4 reactors. The flow model was designed according to the principle of similarity. Obtained from the test were the core inlet flow distribution, the core exit pressure deviations, and the segmental and overall pressure losses across the flow path from the reactor vessel inlet to outlet nozzle. These data will be used to provide input data for the core thermal margin analysis and to verify the analytical hydraulic design method.

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Comfort Analysis of Mono-ski with Hydraulic Absorber (모노스키 유압 완충장치 특성에 따른 탑승 안락감 평가)

  • Cho, Hyeon-Seok;Park, Jin-Kook;Kim, Gyoo-Seok;Mun, Mu-Sung;Kim, Chang-Boo
    • Transactions of the KSME C: Technology and Education
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    • v.3 no.2
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    • pp.131-140
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    • 2015
  • The mono-ski for the paraplegia designed to skiing is formed as seat bucket on the sled. The impact force transferred by snow surface during skiing is absorbed by the leg joints of normal human, but it is transferred to the human body on the seat when using mono-ski. Most of commercially available mono-ski have absorbing device and link mechanism between seat and ski mount in order to complement it. In this study we developed the comfort evaluation model that could provide skiing simulation of mono-ski with hydraulic damper and analyzed vibrational acceleration occurred during skiing uneven surface. The evaluation method used in this study is the international standard BS6841. We evaluated comfort performance of mono-ski in accordance with nozzle adjustment of hydraulic damper.

Analysis on the Internal Flow of the Hydraulic Dual Chambers Applying Various Orifice (다양한 오리피스를 이용한 연결형 공압 챔버 내부 유동 해석)

  • Cho, Kihong;Park, Jungho;Kim, Euiyong
    • Journal of the Korean Society of Propulsion Engineers
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    • v.18 no.1
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    • pp.58-64
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    • 2014
  • Hydraulic dual chamber, as the simulator for a dual pulse rocket motor, was tested by a high pressure device with various orifice-hole size being applied. Pressure difference occurs between 1st chamber and 2nd chamber depending on area ratio of the orifice to nozzle throat. Studying a design configuration of the orifice is essential to the motor development because pressure difference severely affects the rocket motor performance. It is noticed in this study that energy dissipation is caused by the vortex flow originating from the orifice as the 2nd chamber is operated. The flow field is simulated by a commercial computational fluid dynamics program, ANSYS FLUENT V14.5.