• 제목/요약/키워드: Core Flow

검색결과 1,166건 처리시간 0.023초

A FLOW AND PRESSURE DISTRIBUTION OF APR+ REACTOR UNDER THE 4-PUMP RUNNING CONDITIONS WITH A BALANCED FLOW RATE

  • Euh, D.J.;Kim, K.H.;Youn, Y.J.;Bae, J.H.;Chu, I.C.;Kim, J.T.;Kang, H.S.;Choi, H.S.;Lee, S.T.;Kwon, T.S.
    • Nuclear Engineering and Technology
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    • 제44권7호
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    • pp.735-744
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    • 2012
  • In order to quantify the flow distribution characteristics of APR+ reactor, a test was performed on a test facility, ACOP ($\underline{A}$PR+ $\underline{C}$ore Flow & $\underline{P}$ressure Test Facility), having a length scale of 1/5 referring to the prototype plant. The major parameters are core inlet flow and outlet pressure distribution and sectional pressure drops along the major flow path inside reactor vessel. To preserve the flow characteristics of prototype plant, the test facility was designed based on a preservation of major flow path geometry. An Euler number is considered as primary dimensionless parameter, which is conserved with a 1/40.9 of Reynolds number scaling ratio. ACOP simplifies each fuel assembly into a hydraulic simulator having the same axial flow resistance and lateral cross flow characteristics. In order to supply boundary condition to estimate thermal margins of the reactor, the distribution of inlet core flow and core exit pressure were measured in each of 257 fuel assembly simulators. In total, 584 points of static pressure and differential pressures were measured with a limited number of differential pressure transmitters by developing a sequential operation system of valves. In the current study, reactor flow characteristics under the balanced four-cold leg flow conditions at each of the cold legs were quantified, which is a part of the test matrix composing the APR+ flow distribution test program. The final identification of the reactor flow distribution was obtained by ensemble averaging 15 independent test data. The details of the design of the test facility, experiment, and data analysis are included in the current paper.

수평원통 관에서 선회유동의 공기동 발생에 관한 실험적 연구 (An Experimental Study on the Generation of Air-core with Swirl Flow in a Horizontal Circular Tube)

  • 장태현
    • Journal of Advanced Marine Engineering and Technology
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    • 제28권6호
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    • pp.922-930
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    • 2004
  • An experimental investigation was performed to study on the generation of air bubble and air core with swirling flow in a horizontal cicular tube. To determine some characteristics of the flow, 2D PIV technique is employed for velocity measurement in water. The experimental rig is manufactured from an acryl tube. The test tube diameter of 80mm, and a length of 3000mm. The used algorithm is the gray leve cross-correlation method(Kimura et al. 1986). An Ar-ion laser is used and the light from the laser(500mW) passes through a probe to make two-dimensional light sheet. In order to make coded images of the tracer particles on one frame, an AOM(Acoustic-Optical Modulator) is used. The maximum axial velocities showed near the test tube wall at y/D =0.1 and y/D =0.9 along the test tube. The higher Reynolds number increase, the lower axial velocities are showed in the center of the test tube. The air bubbles are generated from Re =10,000 and developed into air core from the recirculating water pump rpm equal 30Hz. The pressure and temperature are measured across the test tube at X/D=3.33.

낮은 종횡비의 직각밀폐용기내의 자연대류 경계층 흐름영역에서의 코어형상에 관한 근사해석 (Analysis of Natural Convection Core Configuration at Boundary Layer Flow Regime in a Low Aspect Ratio Rectangular Enclosure)

  • 이진호;김무현;전주명
    • 대한기계학회논문집
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    • 제12권2호
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    • pp.349-358
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    • 1988
  • 본 연구에서는 낮은 종횡비의 직각밀폐용기의 경계층흐름영역에 대하여 Lee에 의해 공식적인 수학적 방법으로 얻어진 코어방정식을 기초로 코어흐름 형상을 근사해석으로 구하였으며 그 결과를 다른 연구자들의 결과와 비교, 검토하였다.

포텐셜 코어내에 설치된 충돌평판상의 열전달증진 및 유동특성에 관한 연구 (Study on the flow characteristics and heat transfer enhancement on flat plate in potential core region of 2-dimensional air jet)

  • 이용화
    • 설비공학논문집
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    • 제10권2호
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    • pp.193-201
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    • 1998
  • A heat exchanging system employing the impinging air jet is still widely used In the various fields due to its inherent merits that include the easiness in engineering applications and the high heat and/or mass transfer characteristics. The purpose of this study is to investigate the enhancement of heat transfer and flow characteristics by placing a turbulence promoters in front of heat exchanging surface. In this study, a series of circular rods are placed at the upstream of a flat plate heat exchanger that is located at potential core region(H/W=2) of a two-dimensional impinging air jet. Heat transfer enhancement is achieved by inserting turbulence promoter that results in the flow acceleration and disturbance of boundary layer. The average Nusselt number of the flat plate with the turbulence promoters is found to be around 1.42 times higher than that of the flat plate without the turbulence promoters. Based on the results of flow visualization with a smoke wire, it is confirmed that the heat transfer enhancement is caused by the flow separation and disturbance of boundary layer by inserting the turbulence promoter.

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

  • Lee, Kye-Bock;Im, In-Young;Lee, Byung-Jin;Kuh, Jung-Eui
    • Nuclear Engineering and Technology
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    • 제23권3호
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    • pp.340-351
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    • 1991
  • l/5.03 축소 원자로 모델을 이용하여 원자력 발전소 영광 3,4호기를 위한 유동시험을 수행하였다. 이 유동 시험의 목적은 ABB-CE사의 System 80과 영광 3,4호기 원자로 크기의 상대적인 차이로 인해 발생하는 원자로 용기내의 수력학적 영향을 평가하는 것이다. 유동 모델은 상사성 원리에 따라 설계하였다. 이 시험에서 얻은 결과는 노심 입구 유량 분포, 노심 출구 압력 분포, 원자로 입구 노즐에서부터 출구 노즐까지 유동로를 따른 부분 구간 및 전체 압력 손실이다. 이 데이터들은 노심의 열적 여유도 분석에 필요한 입력 자료 제공과 해석적 수력설계 방법의 검증에 이용하게 된다.

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Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor

  • Sun, Lin;Peng, Minjun;Xia, Genglei;Lv, Xing;Li, Ren
    • Nuclear Engineering and Technology
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    • 제49권1호
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    • pp.71-81
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    • 2017
  • When an integral pressurized water reactor is operated under low power conditions, once-through steam generator group operation strategy is applied. However, group operation strategy will cause nonuniform coolant flow distribution at the core inlet and lower plenum. To help coolant flow mix more uniformly, a flow mixing chamber (FMC) has been designed. In this paper, computational fluid dynamics methods have been used to investigate the coolant distribution by the effect of FMC. Velocity and temperature characteristics under different low power conditions and optimized FMC configuration have been analyzed. The results illustrate that the FMC can help improve the nonuniform coolant temperature distribution at the core inlet effectively; at the same time, the FMC will induce more resistance in the downcomer and lower plenum.

75톤 1단 액체로켓엔진 지상시험에서 중앙 물분사가 후류에 미치는 영향 고찰 (A Study of Core Water Injection Effect Influencing Plume in 75 tf $1^{st}$ Stage Liquid Propellant Rocket Engine Ground Test)

  • 문윤완;설우석
    • 항공우주기술
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    • 제10권1호
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    • pp.129-135
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    • 2011
  • 본 연구는 중앙 물분사 방식을 채택한 액체로켓엔진 후류의 냉각에 대해 전산유체역학을 통한 특성을 고찰하였다. 중앙 물분사 방식의 냉각은 측면 물분사 방식과는 달리, 잘 알려져 있지 않기 때문에 다양한 물분사량과 유량을 통해 효율적으로 후류를 냉각시킬 수 있는 조건을 찾았으며, 해석을 통해 후류의 변화 특성을 살펴보았다. 이로부터 물분사 유량이 총추진제 유량의 2배 이상, 위치는 L/De=1.2일 때가 적당함을 알 수 있었다.

공기기둥이 형성된 원통 용기의 내부유동 특성에 관한 수치해석 연구 (Numerical Study of the Characteristics of Internal Flow Including an Air Core in a Cylindrical Tank)

  • 박일석;손종현;손창현
    • 대한기계학회논문집B
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    • 제36권3호
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    • pp.269-276
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    • 2012
  • 액체가 차있는 원통 용기를 회전 시킨 후 바닥 중앙에 위치한 원형 배수구로 액체를 배수시키면 공기 기둥이 형성된다. 공기기둥이 발생하면, 배수 유량이 감소하고 배수 시간도 지연된다. 본 연구에서는 공기기둥 형성과 배수과정 중의 용기내부의 유동특성을 수치해석 방법으로 관찰하였다. 다양한 격자계와 시간차분방법을 적용하였고 적합한 방식을 얻기 위해 실험결과와 비교하였다. 여러 위치에서의 축방향, 반경방향, 원주방향 속도 성분들의 분포를 시간대 별로 나타내었고, 속도 벡터와 유선 분포 도시를 통하여 내부 유동 구조를 분석하였다.

부착 유지장치의 직, 간접 부착법에 따른 전단 접착력 비교 (Direct and indirect bonding of wire retainers to bovine enamel using three resin systems: shear bond strength comparisons)

  • 권태엽;;;박효상
    • 대한치과교정학회지
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    • 제41권6호
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    • pp.447-453
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    • 2011
  • Objective: We compared the shear bond strength (SBS) of lingual retainers bonded to bovine enamel with three different resins using direct and indirect methods. Methods: Both ends of pre-fabricated twisted ligature wires were bonded to bovine enamel surfaces using Light-Core, Tetric N-Flow, or Transbond XT. Phosphoric acid-etched enamel surfaces were primed with One-Step prior to bonding with Light-Core or Tetric N-Flow. Transbond XT primer was used prior to bonding with Transbond XT. After 24 hours in water at $37^{\circ}C$, we performed SBS tests on the samples. We also assigned adhesive remnant index (ARI) scores after debonding and predicted the clinical performance of materials and bonding techniques from Weibull analyses. Results: Direct bonding produced significantly higher SBS values than indirect bonding for all materials. The SBS for Light-Core was significantly higher than that for Tetric N-Flow, and there was no significant difference between the direct bonding SBS of Transbond XT and that of Light-Core. Weibull analysis indicated Light-Core performed better than other indirectly bonded resins. Conclusions: When the SBS of a wire retainer is of primary concern, direct bonding methods are superior to indirect bonding methods. Light-Core may perform better than Transbond XT or Tetric N-Flow when bonded indirectly.

Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor

  • Wang, X.A.;Zhang, Dalin;Wang, Mingjun;Song, Ping;Wang, Shibao;Liang, Yu;Zhang, Yapei;Tian, Wenxi;Qiu, Suizheng;Su, G.H.
    • Nuclear Engineering and Technology
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    • 제52권4호
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    • pp.708-720
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    • 2020
  • Core-wide temperature distribution in sodium-cooled fast reactor plays a key role in its decay heat removal process, however the prediction for temperature distribution is quite complex due to the conjugate heat transfer between the assembly flow and the inter-wrapper flow. Hybrid medium model has been proposed for conjugate heat transfer modeling in the core. The core is modeled with a Realistic modeled inter-wrapper flow and hybrid medium modeled assembly flow. To validate present model, simulations for a three-assembly model were performed with Realistic modeling, traditional porous medium model and hybrid medium model, respectively. The influences of Uniform/Non-Uniform power distribution among assemblies and the Peclet number within the assembly flow have been considered. Compared to traditional porous medium model, present model shows a better agreement with in Realistic modeling prediction of the temperature distribution and the radial heat transfer between the inter-wrapper flow and the assembly flow.