• Title/Summary/Keyword: Air/water test facility

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Development of a prediction model relating the two-phase pressure drop in a moisture separator using an air/water test facility

  • Kim, Kihwan;Lee, Jae bong;Kim, Woo-Shik;Choi, Hae-seob;Kim, Jong-In
    • Nuclear Engineering and Technology
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    • v.53 no.12
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    • pp.3892-3901
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    • 2021
  • The pressure drop of a moisture separator in a steam generator is the important design parameter to ensure the successful performance of a nuclear power plant. The moisture separators have a wide range of operating conditions based on the arrangement of them. The prediction of the pressure drop in a moisture separator is challenging due to the complexity of the multi-dimensional two-phase vortex flow. In this study, the moisture separator test facility using the air/water two-phase flow was used to predict the pressure drop of a moisture separator in a Korean OPR-1000 reactor. The prototypical steam/water two-phase flow conditions in a steam generator were simulated as air/water two-phase flow conditions by preserving the centrifugal force and vapor quality. A series of experiments were carried out to investigate the effect of hydraulic characteristics such as the quality and liquid mass flux on the two-phase pressure drop. A new prediction model based on the scaling law was suggested and validated experimentally using the full and half scale of separators. The suggested prediction model showed good agreement with the steam/water experimental results, and it can be extended to predict the steam/water two-phase pressure drop for moisture separators.

Air-Water Test on the Direct ECC Bypass During LBLOCA Reflood Phase with DVI : UPTF Test 21-D Counterpart Test

  • Yun, Byong-Jo;Kwon, Tae-Soon;Song, Chul-Hwa;Euh, Dong-Jin;Park, Jong-Kyun;Cho, Hyoung-Kyu;Park, Goon-Cherl
    • Nuclear Engineering and Technology
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    • v.33 no.3
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    • pp.315-326
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    • 2001
  • Direct ECC bypass phenomena that occur in a reactor vessel downcomer with a Direct Vessel Injection (DVI) system during the reflood phase of a Large Break Loss-of-Coolant Accident (LBLOCA) are experimentally investigated using a transparent l/7.5 scaled down test facility of the Upper Plenum Test Facility (UPTF). A series of separate effect tests are peformed in order to investigate the mechanisms of direct ECC bypass and to find out its scaling parameters. Various flow regimes and phasic distribution in downcomer are identified and mapped, and the fraction of direct ECC bypass is measured under a wide range of air and water injection conditions. From the counterpart test of the UPTF Test 21-D, the dimensionless gas velocity ( $j^{*}$$_{g,eff}$) is derived experimentally, which is believed to be a major scaling parameter for the fraction of direct ECC bypass. And it is found out that the direct ECC bypass is greatly affected by the spreading width of ECC water film and the geometric configuration of the downcomer.r.

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Development of Turbopump Cavitation Performance Test Facility and the Test of Inducer Performance (터보펌프 Cavitation 성능시험기 개발 및 성능시험에 관한 연구)

  • Sohn, Dong-Kee;Kim, Chun-Tak;Yoon, Min-Soo;Cha, Bong-Jun;Kim, Jin-Han;Yang, Soo-Seok
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.619-624
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    • 2001
  • A performance test facility for turbopump inducer cavitation was developed and the inducer cavitation performance tests were performed. Major components of the performance test facility are driving unit, test section, piping, water tank, and data acquisition and control system. The maximum of testing capability of this facility are as follows: flow rate - 30kg/s; pressure - 13 bar; rotational speed 10,000rpm. This cavitation test facility is characterized by the booster pump installed at the outlet of the pump that extends the flow rate range, and by the pressure control system that makes the line pressure down to vapor pressure. The vacuum pump is used for removing the dissolved air in the water as well as the line pressure. Performance tests were carried out and preliminary data of test model inducer were obtained. The cavitation performance test and cavitation bubble flow visualization were also made. This facility is originally designed for turbopump inducer performance test and cavitation test. However it can be applied to the pump impeller performance test in the future with little modification.

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Fundamental design consideration for optimum performance in altitude test cell facility (고공시험설비의 전체 사양을 결정하는 시험부를 중심으로 설비개발시의 주요 고려사항)

  • Choi, Kyoung-Ho;Lee, Jung-Hyung;Owino, George;Lee, Dae-Soo
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2008.11a
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    • pp.411-415
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    • 2008
  • This paper presents on design factor considered in an altitude test cell facility to determine the best sizing to optimize exhaust diffuser pressure recovery and the exact cooling load required to be supplied under transient operation. Engine simulation was performed to analyse the exhaust gas temperature, exit mass flow rate, specific fuel consumption and exhaust velocity helpful in determining secondary mass air flow and the mixed air temperature entering the ejector. based on this, the amount of cooling load was deduced. It was found that improved pressure recovery reduces operational cost(air supply facility, cooling water).

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An Analysis on Plume Behaviour of Rocket Engine with Ground Condition at High Altitude Engine Test Facility (고공시험설비에서 로켓엔진의 지상시험 플룸 거동 해석)

  • Kim, Seong-Lyong;Lee, SeungJae;Han, YoungMin
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2017.05a
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    • pp.112-115
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    • 2017
  • We analyzed the rocket engine flow to check whether the possibility of the ground test and the equipment safety problems in the high altitude engine test facility. The test condition is that the vacuum chamber is open and the coolant water is injected into the supersonic diffuser. The analysis uses two-dimensional axisymmetry with a mixture of plume, air, and cooling water. As a result, the ground test was possible up to the cooling water flow rate of 200 kg/sec. However, due to the back flow of the initial plume, the vacuum chamber is exposed to high temperature, and at the same time, the inside of the vacuum chamber is contaminated due to the reverse flow of the cooling water. Therefore, sufficient insulation measures and work for pollution avoidance should be preceded.

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ASSESSMENT OF A NEW DESIGN FOR A REACTOR CAVITY COOLING SYSTEM IN A VERY HIGH TEMPERATURE GAS-COOLED REACTOR

  • PARK GOON-CHERL;CHO YUN-JE;CHO HYOUNGKYU
    • Nuclear Engineering and Technology
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    • v.38 no.1
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    • pp.45-60
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    • 2006
  • Presently, the VHTGR (Very High Temperature Gas-cooled Reactor) is considered the most attractive candidate for a GEN-IV reactor to produce hydrogen, which will be a key resource for future energy production. A new concept for a reactor cavity cooling system (RCCS), a critical safety feature in the VHTGR, is proposed in the present study. The proposed RCCS consists of passive water pool and active air cooling systems. These are employed to overcome the poor cooling capability of the air-cooled RCCS and the complex cavity structures of the water-cooled RCCS. In order to estimate the licensibility of the proposed design, its performance and integrity were tested experimentally with a reduced-scale mock-up facility, as well as with a separate-effect test facility (SET) for the 1/4 water pool of the RCCS-SNU to examine the heat transfer and pressure drop and code capability. This paper presents the test results for SET and validation of MARS-GCR, a system code for the safety analysis of a HTGR. In addition, CFX5.7, a computational fluid dynamics code, was also used for the code-to-code benchmark of MARS-GCR. From the present experimental and numerical studies, the efficacy of MARS-GCR in application to determining the optimal design of complicated systems such as a RCCS and evaluation of their feasibility has been validated.

Air-Water Two-Phase Flow Test Facility of a Single Stage Closed-type Centrifugal Pump (단단 밀폐형 원심펌프의 기액이상류 성능시험 설비)

  • Kim, S. Y.;Lee, S. L.;Kim, Y. T.;Kim, S. D.;Lee, Y. S.;Lee, Y. H.
    • 유체기계공업학회:학술대회논문집
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    • 2004.12a
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    • pp.49-53
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    • 2004
  • LabVIEW is mostly preferred to use in experiment, measurement and control as one of the useful thing in America and Europe. So, We tried performance experiment of a single-stage closed-type centrifugal pump by using the LabVIEW. The pump rpm and the shaft torque are measured by rpm sensor and torque sensor The test pump's maximum rpm, head, kW are 1,750, 13m, and 1.5kW, respectively The casing is made up with transparency acrylic for confirmation the flow patterns. We installed experimental equipment for air water two phase flow. This paper tries to analyze the single-phase flow characteristics through this air water two phase flow experimental apparatus. The performance results of a single-stage closed-type centrifugal pump satisfied reappearance and coincide well with head and coefficients according to the change of rpm.

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A Study on the Performance of Water Mist Spray Fire Protection System (미세물분무 소화성능에 관한 연구)

  • 김봉환;김용판;문철진;홍철현;이형욱;최현호
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.15 no.7
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    • pp.572-578
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    • 2003
  • The present study was numerically and experimentally performed to investigate the fire suppression performance of water mist spray subjected to thermal radiation in closed space. Downward-directed water mist sprays to interact with an under kerosine pool fire were investigated in test facility The mass mean diameters of water mist droplet were measured by PMAS under various flow conditions. The developed water mist spray nozzle was satisfied to the criteria of NFPA 750, Class 1. The mechanism of the fire suppression by water mist was attributed to the cooling of the fire surface which lead to suppressed of fuel evaporation. It was proved that the water mist spray system under lower pressures could be applied to underground fire protection system.

Experimental Approach for Water Discharge Characteristics at PEMFC by using Neutron Imaging Technique considered Neutron Flux and Linear Attenuation Coefficient of Thermal Neutron Correction at NRF, HANARO (중성자속 및 선형 흡수 계수 보정을 고려한 중성자영상법을 이용한 PEMFC 내의 물 배출 특성에 관한 실험적 연구)

  • Kim, Tae-Joo;Kim, Jong-Rok;Kim, Moo-Hwan;Sim, Cheul-Muu
    • Proceedings of the KSME Conference
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    • 2007.05b
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    • pp.3418-3422
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    • 2007
  • The neutron imaging technique was used to investigate the water discharge characteristics at PEMFC. Prior to investigation of water discharge characteristics, the linear attenuation coefficient for water at Neutron Radiography Facility (NRF) was calibrated. The feasibility test apparatus was consisted of pressurized air and water in order to simulate the actual operating PEMFC. The feasibility tests have been performed at 1-parallel serpentine type with 100 $cm^2$ active area and different air flow rate (1, 2, and 4 lpm). The total water volume variations at each condition were calculated from the neutron images. The water at channel is well discharged as soon as supplying the pressurized air into the PEMFC. However, because the water at MEA isn't removed the total water volume is constant after 150. Therefore more effective method is needed in order to discharge water at MEA, and the neutron imaging technique is helpful for it.

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A Study of the Evaporation Heat Transfer in Advanced Reactor Containment

  • Y. M. Kang;Park, G. C.
    • Nuclear Engineering and Technology
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    • v.29 no.4
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    • pp.291-298
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    • 1997
  • In advanced nuclear reactors, the passive containment cooling has been suggested to enhance the safety. The passive cooling has two mechanisms, air natural convection and oater cooling with evaporation. To confirm the coolability of PCCS, many works have been performed experimentally and numerically. In this study, the water cooling test was performed to obtain the evaporative heat transfer coefficients in a scaled don segment type PCCS facility which have same configuration with AP600 prototype containment. Air-steam mixture temperature and velocity, relative humidity and well heat flux are measured. The local steam mass flow rates through the vertical plate part of the facility are calculated from the measured data to obtain evaporative heat transfer coefficients. The measured evaporative heat transfer coefficients are compared with an analytical model which use a mass transfer coefficients. From the comparison, the predicted coefficients show good agreement with experimental data however, some discrepancies exist when the effect of wave motion is not considered. Finally, a new correlation on evaporative heat transfer coefficients are developed using the experimental values.

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