• Title/Summary/Keyword: Flow Tube

Search Result 2,184, Processing Time 0.033 seconds

Study on the Flow of Briquette Gas in the Ondol Heating System (2) (Gas Flow in a Briquette Flue Tube) (온돌의 연탄개스유량에 관한 연구 (2) (유도연관내의 개스유동))

  • Min, Man-Gi;Jeong, Jae-Seon
    • The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
    • /
    • v.4 no.4
    • /
    • pp.275-284
    • /
    • 1975
  • By the experiment of a model Ondol heating system gas flow characteristics in a briquette flue tube was investigated. As a heat source electric heater was used, which renders steady flow condition of air. working fluid. It was observed that the flow augumentation may be obtained by increasing the vertial elevation of the flue tube, namely increase in the tube length or increase in the tube inclination, and the gas temperature at the tube entrance Among several factors which augument the flow rate slope of the flue tube has the most striking effect and then the temperature of gas entering the tube. Increase in length of the tube also auguments the flow but the rate of augumentation is so small that it gives little assistance to improvement of the flow The flow in a briguette flue gas does not essentially satisfy the one dimensional steady flow assumption. It is also observed that the flow begins to accompany irregular velocity fluctuation as inclination of the tube increases.

  • PDF

Flow Distribution in the Core of the HANARO After Suppressing the Jet Flow in the Guide Tube used for Loading Fission Moly Target. (Fission Moly 표적을 장전하기 위한 안내관의 제트유동 억제 후 하나로 노심유량분포)

  • Park Yong-Chul;Lee Byung-Chul;Kim Bong-Soo;Kim Kyung-Ryun
    • 한국전산유체공학회:학술대회논문집
    • /
    • 2005.04a
    • /
    • pp.70-73
    • /
    • 2005
  • The HANARO, multi-purpose research reactor, 30 MWth open-tank-in-pool type, is planning to produce a fission moly-99 of radio isotopes, a mother nuclide of Tc-99m, a medical isotope and is under developing a target handling tool for loading and unloading it in a circular flow tube (OR-5). A guide tube is extended from the reactor core to the top of the reactor chimney for easily loading the target under the reactor normal operation. But active coolant through the core can be quickly raised up to the top of the chimney through the guide tube. The jet flow was suppressed in the guide tube after reducing the inner diameter of a flow restriction orifice installed in the OR-5 flow tube for adding the pressure difference in the flow tube after unloading the target. This paper describes an analytical analysis to calculate the flow distribution in the core of the HANARO after suppressing the jet flow of the guide tube. As results, it was confirmed through the analysis results that the flow distribution in the core of the HANARO were not adversely affected.

  • PDF

FLOW DISTRIBUTION IN THE CORE OF HANARO AFTER SUPPRESSING THE JET FLOW IN THE GUIDE TUBE USED FOR LOADING FISSION MOLY TARGET (Fission Moly 표적을 장전하기 위한 안내관의 제트유동 억제 후 하나로 노심 유량분포)

  • Park Yong Chul;Lee Byung Chul;Kim Bong Soo;Kim Kyung Ryun
    • Journal of computational fluids engineering
    • /
    • v.10 no.4 s.31
    • /
    • pp.66-71
    • /
    • 2005
  • HANARO, a multi-purpose research reactor, 30 MWth open-tank-in-pool type, is planning to produce a fission moly-99 of radio isotopes, a mother nuclide of Tc-99m, a medical isotope and a target handling tool is under development for loading and unloading it in a circular flow tube (OR-5) of HANARO. A guide tube is extended from the reactor core to the top of the reactor chimney for easily loading the target under a normal operation of the reactor. But active coolant through the core can be quickly raised up to the top of the chimney through the guide tube. The jet flow was suppressed in the guide tube after reducing the inner diameter of a flow restriction orifice installed in the OR-5 flow tube for adding the pressure difference in the flow tube. This paper describes an analytical analysis to calculate the flow distribution in the core of HANARO after suppressing the jet flow of the guide tube. As results, it was confirmed through the analysis results that the flow distribution in the core of HANARO were not adversely affected.

Mechanism analysis on fluidelastic instability of tube bundles in considering of cross-flow effects

  • Lai, Jiang;Sun, Lei;Gao, Lixia;Li, Pengzhou
    • Nuclear Engineering and Technology
    • /
    • v.51 no.1
    • /
    • pp.310-316
    • /
    • 2019
  • Fluidelastic instability is a key issue in steam generator tube bundles subjected in cross-flow. With a low flow velocity, a large amplitude vibration of the tube observed by many researchers. However, the mechanism of this vibration is seldom analyzed. In this paper, the mechanism of cross-flow effects on fluidelastic instability of tube bundles was investigated. Analysis reveals that when the system reaches the critical state, there would be two forms, with two critical velocities, and thus two expressions for the critical velocities were obtained. Fluidelastic instability experiment and numerical analysis were conducted to obtain the critical velocity. And, if system damping is small, with increases of the flow velocity, the stability behavior of tube array changes. At a certain flow velocity, the stability of tube array reaches the first critical state, a dynamic bifurcation occurs. The tube array returns to a stable state with continues to increase the flow velocity. At another certain flow velocity, the stability of tube array reaches the second critical state, another dynamic bifurcation occurs. However, if system damping is big, there is only one critical state with increases the flow velocity. Compared the results of experiments to numerical analysis, it shows a good agreement.

The Analytic Analysis of Suppressing Jet Flow at Guide Tube of Circular Irradiation Hole in HANARO (하나로 원형 조사공의 안내관 제트유동 억제에 대한 해석)

  • Park Y. C.;Wu S. I.
    • 한국전산유체공학회:학술대회논문집
    • /
    • 2004.03a
    • /
    • pp.214-219
    • /
    • 2004
  • The HANARO, a multi-purpose research reactor of 30 MWth, open-tank-in-pool type, has been under normal operation since its initial criticality in February, 1995. The HANARO is composed of inlet plenum, grid plate, core channel with flow tubes and chimney. The reactor core channel is located at about twelve m (12 m) depth of the reactor pool and cold by the upward flow that the coolant enters the lower inlet of the plenum, rises up through the grid plate and the core channel and exit through the outlet of chimney. A guide tube is extended from the reactor core to the top of the reactor chimney for easily un/loading a target under the reactor normal operation. But active coolant through the core can be Quickly raised up to the top of the chimney through the guide tube by jet flow. This paper is described an analytical analysis to study the flow behavior through the guide tube under reactor normal operation and unloading the target. As results, it was conformed through the analysis results that the flow rate, about fourteen kilogram per second (14 kg/s) suppressed the guide tube jet and met the design cooling flow rate in a circular flow tube, and that the fission moly target cooling flow rate met the minimum flow rate to cool the target.

  • PDF

Characteristics of Refrigerant Flow through Capillary Tubes and Short Tube Orifices

  • Kim, Yong-Chan;Choi, Jong-Min
    • International Journal of Air-Conditioning and Refrigeration
    • /
    • v.7
    • /
    • pp.11-21
    • /
    • 1999
  • The capillary tube and short tube orifice have been widely used as an expansion device in the refrigeration and air-conditioning system. To improve the system performance, expansion devices need to be optimized with the components of a refrigeration system. In the present study, a numerical model for a capillary, which could predict the flow rate and properties along a tube, was developed by assuming homogeneous two-phase flow. A semi-empirical flow model for evaluation of the flow rate through a short tube orifice was also developed by using the experimental data. Finally, the results of the numerical model for a capillary was compared with those of the semi-empirical model for a short tube orifice to identify the dominant flow factors for the expansion devices.

  • PDF

FLUID-ELASTIC INSTABILITY OF ROTATED SQUARE TUBE ARRAY IN AN AIR-WATER TWO-PHASE CROSSFLOW

  • CHUNG HEUNG JUNE;CHU IN-CHEOL
    • Nuclear Engineering and Technology
    • /
    • v.38 no.1
    • /
    • pp.69-80
    • /
    • 2006
  • Fluid-elastic instability in an air-water two-phase cross-flow has been experimentally investigated using two different arrays of straight tube bundles: normal square (NS) array and rotated square (RS) array tube bundles with the same pitch-to-diameter ratio of 1.633. Experiments have been performed over wide ranges of mass flux and void fraction. The quantitative tube vibration displacement was measured using a pair of strain gages and the detailed orbit of the tube motion was analyzed from high-speed video recordings. The present study provides the flow pattern, detailed tube vibration response, damping ratio, hydrodynamic mass, and the fluid-elastic instability for each tube bundle. Tube vibration characteristics of the RS array tube bundle in the two-phase flow condition were quite different from those of the NS array tube bundle with respect to the vortex shedding induced vibration and the shape of the oval orbit of the tube motion at the fluid-elastic instability as well as the fluid-elastic instability constant.

Flow-induced instability and nonlinear dynamics of a tube array considering the effect of a clearance gap

  • Lai, Jiang;Sun, Lei;Li, Pengzhou
    • Nuclear Engineering and Technology
    • /
    • v.51 no.6
    • /
    • pp.1650-1657
    • /
    • 2019
  • Fluidelastic instability and nonlinear dynamics of tube bundles is a key issue in a steam generator. Especially, once the post-instability motion of the tube becomes larger than the clearance gap to other tubes, effective contact or impact between the tubes under consideration and the other tube inevitable. There is seldom theoretical analysis to the nonlinear dynamic characteristics of a tube array in two-phase flow. In this paper, experimental and numerical studies were utilized to obtain the critical velocity of the flow-induced instability of a rotated triangular tube array. The calculation results agreed well with the experimental data. To explore the post-instability dynamics of the tube array system, a Runge-Kutta scheme was used to solve the nonlinear governing equations of tube motion. The numerical results indicated that, when the flow pitch velocity is larger than the critical velocity, the tube array system is undergoing a limit cycle motion, and the dynamic characteristics of the tube array are almost similar for different void fractions.

Flow Analyses using FLUENT 5.4 Code for the Bi-directional Flow Tube (FLUENT 5.4 코드를 이용한 양방향 유동 튜브에 대한 유동해석)

  • Kang, Kyoung-Ho;Yun, Byung-Jo;Baek, Won-Pil
    • Proceedings of the KSME Conference
    • /
    • 2003.11a
    • /
    • pp.934-938
    • /
    • 2003
  • Flow analyses using FLUENT 5.4 code were performed to validate the application of the local bidirectional flow tube in case of water and air flow. In this study, sensitivity studies have been performed to optimize the design features of the bi-directional flow tube which can be applied for the various experimental conditions. 2-dimensional axisymmetric steady state flow analyses have been performed. By calculating the differential pressure at both the front and the rear hole of the flow tube, K values were evaluated. The K values show good linearity regardless of the tube sizes and the Re numbers in both water and air flow. And system pressure and water subcooling didn’'t affect the K values. Under the elevated pressure of 80bar with 80K water subcooling, the K value indicates a similar trend with the case of 2bar with 80K water subcooling.

  • PDF

An Experimental Study on Flow Angle with Swirl in a Horizontal Circular Tube (수평 원통 관에서 선회를 동반한 유동각에 대한 실험적 연구)

  • Chang, Tae-Hyun
    • Journal of the Korean Society of Manufacturing Process Engineers
    • /
    • v.2 no.4
    • /
    • pp.82-87
    • /
    • 2003
  • Flow angle with Swirl in a horizontal circular tube and a cylindrical annuli were experimentally studied for its visualization. This present investigation deals with flow angle, flow visualization studies and vortex core by using oil smoke and a hot wire anemometer for Re = 40,000 and 50000 at X/D = 41, 59 and 71 in a horizontal circular tube. In the swirl air flow, a vortex core was formed at high swirl intensity along the test tube. The flow angle and the vortex core depended on the swirl intensity along the test tube. The results of flow angles with swirl measured by flow visualization and hot wire reasonably agree with those of Sparrow One of the primary objectives of this research was to measure the flow angle with swirl in a cylindrical annuli along the test tube for different Reynolds numbers. The Reynolds number for these measurements ranged from 60,000 to 100,000 with L/D = a to 4.

  • PDF