• Title/Summary/Keyword: Fluid Transients

Search Result 42, Processing Time 0.024 seconds

Effects of the Air Volume in the Air Chamber on the Performance of Water Hammer Pump System

  • Saito, Sumio;Takahashi, Masaaki;Nagata, Yoshimi
    • International Journal of Fluid Machinery and Systems
    • /
    • v.4 no.2
    • /
    • pp.255-261
    • /
    • 2011
  • Recently, as global-scale problems, such as global warming and energy depletion, have attracted attention, the importance of future environmental preservation has been emphasized worldwide, and various measures have been proposed and implemented. This study focuses on water hammer pumps that can effectively use the water hammer phenomenon and allow fluid transport without drive sources, such as electric motors. An understanding of operating conditions of water hammer pumps and an evaluation of their basic hydrodynamic characteristics are significant for determining whether they can be widely used as an energy-saving device in the future. However, conventional studies have not described the pump performance in terms of pump head and flow rate, common measures indicating the performance of pumps. As a first stage for the understanding of water hammer pump performance in comparison to the characteristics of typical turbo pumps, the previous study focused on understanding the basic hydrodynamic characteristics of water hammer pumps and experimentally examined how the hydrodynamic characteristics were affected by the inner diameters of the drive and lift pipes and the angle of the drive pipe. This paper suggests the effect of the air volume in the air chamber that affects the hydrodynamic characteristics and operating conditions of the water hammer pump.

A Study on the Associated Response Lag in Shock Control of Hydraulic System Using Fluid Device (유체기구를 이용한 유압계통의 충격치제어에 수탄되는 반응지연에 관한 연구)

  • Lee, Joo-Seong;Lee, Kye-Bock
    • Transactions of the Korean Society of Mechanical Engineers B
    • /
    • v.26 no.11
    • /
    • pp.1488-1495
    • /
    • 2002
  • The response time represents how fast a system responds to a given disturbance at the system boundary. Flow restricting devices for controlling transients can result in a decrease in the peakm pressure, but may change response time. Response lag in a hydraulic system leads to inefficient working cycle and operator discomfort. The experiments were conducted in order to get information on the parameters which exert appreciable influence on the response time. The experimental apparatu including a hydraulic actuator, orifice and a hydraulic pump was an idealization of a bucket hydraulic shifting system. Experimental results show that the response time depends on operating pressure and flow rate. The effects of orifice type and size on the response time are quantified.

A Study on the Response Time Characteristics Related to Shock Control in the Hydraulic System Using the Fluid Device (유체기구를 이용한 유압계통의 충격치제어에 수반되는 응답시간 변화특성에 관한 연구)

  • Lee, Joo-Seong;Lee, Kye-Bock;Lee, Chung-Gu
    • Proceedings of the KSME Conference
    • /
    • 2001.11b
    • /
    • pp.597-603
    • /
    • 2001
  • Control of pressure transients in a hydraulic system may be important and necessary to avoid failures and to improve the efficiency of operation. Flow restricting devices can result in a decrease in the peak pressure, but may change the response time. The response time has an important effect on both operator and operator perceived smoothness. The response time should correspond to how fast a system responds to a given disturbance at the system boundary. Occasionally the appropriate response time is not easily determined. This study is on the response time characteristics in the hydraulic system studied for the control of response time.

  • PDF

3-Dimensional Numerical Analysis for Thermal Stratification in Surgeline in Nuclear Power Plant (원전 밀림관 열성층의 3 차원 수치해석)

  • Kim, Young-Jong;Kim, Maan-Won;Ko, Eun-Mi
    • Proceedings of the KSME Conference
    • /
    • 2008.11a
    • /
    • pp.729-734
    • /
    • 2008
  • A thermal stratification may occur in the horizontal parts of the surge line during operating transients of the pressurizer, which produces relatively high fatigue usage factor. Heat-up transient is the most severe case among the transient conditions. In this study, to study the relationship between the magnitude of thermal stratification and the length of vertical part of the surge line, some parametric fluid-structure interaction (FSI) analyses with different length variables of the vertical part of the surge line were performed for plant heat-up transient condition by using 3-dimensional numerical analysis. The conservativeness of the traditional finite element model for thermal stratification analysis based on the conservative assumption in the surge line was also discussed by comparison of the results of 3-dimensional transient FSI analysis of this study. Stresses calculated with 3-dimensional transient model were considerably reduced comparing with the traditional analysis.

  • PDF

Waterhammer for In-line Booster Pump (직결식 펌프의 수격현상)

  • Kim, Sang-Gyun;Lee, Gye-Bok;Kim, Kyung-Yup
    • The KSFM Journal of Fluid Machinery
    • /
    • v.8 no.6 s.33
    • /
    • pp.7-14
    • /
    • 2005
  • The waterhammer occur when the pumps are started or stopped for the operation or tripped due to the power failure, and the hydraulic transients take place as a result of the sudden change in velocity. Several times, the field tests of the waterhammer were carried out for Pangyo booster pumping station. Pangyo pumping station was installed with the booster pumps of 6 sets and the in-line pumps of 2 sets. The in-line pumps are additionally needed to the surge suppression device so that the pumping station acquire the safety and reliability for the pressure surge.

SPECTRAL ELEMENT DYNAMIC ANALYSIS OF THE PIPELINE CONVEYING INTERNAL UNSTEADY FLOW (비정상류가 흐르는 파이프의 스펙트럴 요소 동역학 해석)

  • Seo, Bo-Sung;Cho, Joo-Yong;Lee, U-Sik
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
    • /
    • 2005.11a
    • /
    • pp.925-928
    • /
    • 2005
  • In this paper, a spectral element model is developed for the uniform straight pipelines conveying internal unsteady fluid. The spectral element matrix is formulated by using the exact frequency-domain solutions of the pipe-dynamics equations. The spectral element dynamic analyses are then conducted to evaluate the accuracy of the present spectral element model and to investigate the vibration characteristics and internal fluid transients of an example pipeline system.

  • PDF

Prediction of Heat Transfer Rates to Spray Water Droplets in a High Pressure Mixture Composed of Saturated Steam and Noncondensable Hydrogen Gas (고압의 포화수증기-비응축성 수소기체 혼합기 속에서 분무수적으로의 열전달을 예측)

  • Lee, S.K.;Jo, J.C.;Cho, J.H.
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
    • /
    • v.3 no.5
    • /
    • pp.337-349
    • /
    • 1991
  • Heat and mass transfer rates to spray water droplets for spray transients in a high pressure vessel have been predicted by two different droplet models: the complete mixing model and the non-mixing model. In this process, the ambient fluid surrounding the droplets is a real-gas mixture composed of saturated steam and noncondensable hydrogen gas at high pressure. The physical properties of the mixture are estimated by applying the concept of compressibility factor and using appropriate correlations. A computer program, DROPHMT, to calculate the heat and mass transfer rates for two different droplet models has been developed. As an illustrative application of the computer program to engineering practices, heat and mass transfer rates to spray water droplets for spray transients in a Pressurized Water Reactor (PWR) pressurizer have been calculated, and the typical results have been provided.

  • PDF

OVERVIEW OF RECENT EFFORTS THROUGH ROSA/LSTF EXPERIMENTS

  • Nakamura, Hideo;Watanabe, Tadashi;Takeda, Takeshi;Maruyama, Yu;Suzuki, Mitsuhiro
    • Nuclear Engineering and Technology
    • /
    • v.41 no.6
    • /
    • pp.753-764
    • /
    • 2009
  • JAEA started the LSTF experiments in 1985 for the fourth stage of the ROSA Program (ROSA-IV) for the LWR thermal-hydraulic safety research to identify and investigate the thermal-hydraulic phenomena and to confirm the effectiveness of ECCS during small-break LOCAs and operational transients. The LSTF experiments are underway for the ROSA-V Program and the OECD/NEA ROSA Project that intends to resolve issues in thermal-hydraulic analyses relevant to LWR safety. Six types of the LSTF experiments have been done for both the system integral and separate-effect experiments among international members from 14 countries. Results of four experiments for the ROSA Project are briefly presented with analysis by a best-estimate (BE) code and a computational fluid dynamics (CFD) code to illustrate the capability of the LSTF and codes to simulate the thermal-hydraulic phenomena that may appear during SBLOCAs and transients. The thermal-hydraulic phenomena dealt with are coolant mixing and temperature stratification, water hammer up to high system pressure, natural circulation under high core power condition, and non-condensable gas effect during asymmetric SG depressurization as an AM action.

Heat Transfer Characteristics of an Internally-Heated Annulus Cooled with R-134a Near the Critical Pressure

  • Hong, Sung-Deok;Chun, Se-Young;Kim, Se-Yun;Baek, Won-Pil
    • Nuclear Engineering and Technology
    • /
    • v.36 no.5
    • /
    • pp.403-414
    • /
    • 2004
  • An experimental study of heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) tests, and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with increase of the system pressure for fixed inlet mass flux and subcooling. The CHF falls sharply at about 3.8 MPa and shows a trend towards converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall, because the CHF occurs at remarkably low power levels. In the pressure reduction transients, as soon as the pressure passes below the critical pressure from the supercritical pressure, the wall temperatures rise rapidly up to very high values due to the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, and then tends to decrease gradually.

Waterhammer Caused by Startup and Stoppage of a Centrifugal Pump (원심펌프의 시동 및 정지에 따른 수격현상)

  • Kim, Kyung-Yup;Kim, Joum-Bea
    • The KSFM Journal of Fluid Machinery
    • /
    • v.7 no.1 s.22
    • /
    • pp.51-57
    • /
    • 2004
  • The waterhammer has recently become more important because the pumping stations were big and the systems conveying the fluid through the large and long transmission pipelines were complex. When the pumps are started or stopped for the operation or tripped due to the power failure, the hydraulic transients occur as a result of the sudden change in velocity As the pressure waves are propagating between the pumping station and the distributing reservoir, the pressure inside the pipe drops to the liquid vapor pressure with the pipeline profile, at which time a vapor cavity forms, and finally the column separation occurs. If the pressure in the pipe is less than the atmospheric pressure, the pipe can be collapsed and destroyed after the water columns separated by the vapor cavity rejoin. During the reverse flow, the pressure is so abnormally increased at the pumping station that the accident of flooding may happen due to the failure of system. In this paper, the field tests on the waterhammer by the startup, stoppage, and power failure of a centrifugal pump were carried out for Yongma transmission pumping station in Seoul. The experimental results were compared with that of the numerical calculations, in which results the procedure of controlled pump normal shut-down and the two-step closing mode of controlling the ball valve for pump emergency stop are proposed to reduce the pressure surge.