• Title/Summary/Keyword: Pipe Network Analysis

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Numerical Study for The Critical-Flow-Characteristics of The Pressure Regulator and Considerations as a Pipe Network Element (II);Influence of the Cross-Sectional-Area and Opening Ratio (정압기 임계유동특성 및 배관망해석 요소로서의 고려에 관한 수치해석적 연구(II);단면적 및 개도 변화)

  • Shin, C.H.;Ha, J.M.;Lee, C.G.;Her, J.Y.;Im, J.H.;Joo, W.G.
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.1454-1459
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    • 2004
  • The major parameters governing the fluid dynamical and thermo-dynamical behavior in the large pipeline network system are friction loss and the pipeline length. But in local pipeline networks and relatively short distance pipeline system, secondary loss and the considerations of the moving states of the fluid machine are also important. One of the major element in local pressure control system is pressure regulator. It causes the variations of the physical properties in that pipeline system. When it is under working, the accurate analysis of the flow properties is so difficult. In this study, some numerical approaches to investigate the critical-flow-characteristics of the pressure regulator have been done according to the variations of the opening ratio or cross-sectional area and the detail examinations and considerations of the pressure regulator as a pipeline network elements have been carried. Finally the flow-flied distributions and critical-flow-characteristics have been presented in detail and the critical flow phenomena and the relation to the opening ratio or cross-sectional-area ratio have been studied.

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Comparison of the Node Method and the Pipeline Method for the Analysis of Water Distribution Systems (배수관망해석(配水管網解析)에 있어서 절점유출법(節点流出法)과 관로유출법(管路流出法)의 비교(比較))

  • Lee, Sang Mok;Lyu, Jong Hyun;Hyun, In Hwan
    • Journal of Korean Society of Water and Wastewater
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    • v.10 no.4
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    • pp.85-93
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    • 1996
  • This study is to make a comparison between the node method and the pipeline method for the analysis of the water distribution systems. For these purposes, the two methods were applied to a pipeline system in series, an artificial distribution network and a real distribution network. The results are as follows. 1. The difference between the results of the two methods was increased with the increase of the hydraulic gradient and the length between two adjacent nodes. 2. When all pipe lengths between two adjacent nodes were larger than 200~300m and have the steep hydraulic gradient, it was found that the results of the two methods showed high differences. 3. The difference between the results of the two methods were negligible in the case of the real distribution system in which only 12% whole pipelines were longer than 30m and the longest pipe length was 850m.

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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system

  • Wang, Chenglong;Sun, Hao;Tang, Simiao;Tian, Wenxi;Qiu, Suizheng;Su, Guanghui
    • Nuclear Engineering and Technology
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    • v.52 no.1
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    • pp.19-26
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    • 2020
  • Small nuclear reactor features higher power capacity, longer operation life than conventional power sources. It could be an ideal alternative of existing power source applied for special equipment for terrestrial or underwater missions. In this paper, a 25kWe heat pipe cooled reactor power source applied for multiple use is preliminary designed. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor. For reactor design, UN fuel with 65% enrichment and potassium heat pipes are adopted in the reactor core. Tungsten and LiH are adopted as radiation shield on both sides of the reactor core. The reactor is controlled by 6 control drums with B4C neutron absorbers. Thermoelectric generator (TEG) converts fission heat into electricity. Cooling water removes waste heat out of the reactor. The thermal-hydraulic characteristics of heat pipes are simulated using thermal resistance network method. Thermal parameters of steady and transient conditions, such as the temperature distribution of every key components are obtained. Then the postulated reactor accidents for heat pipe cooled reactor, including power variation, single heat pipe failure and cooling channel blockage, are analyzed and evaluated. Results show that all the designed parameters satisfy the safety requirements. This work could provide reference to the design and application of the heat pipe cooled nuclear power source.

Leak and Leak Point Prediction by Detecting Negative Pressure Wave in High Pressure Piping System (저압확장파 검출을 통한 배관 누출 및 누출위치 예측)

  • Ha, Tae-Woong;Ha, Jong-Man;Kim, Dong-Hyuk;Kim, Young-Nam
    • Journal of the Korean Institute of Gas
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    • v.11 no.4
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    • pp.47-53
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    • 2007
  • The safe operation of high pressure pipe line systems is of significant importance. Leaks due to faulty operation from the pipelines can lead to considerable product losses and to exposure of community to dangerous gases. There are several leak detection methods, which have been recently suggested on pipeline network. The negative pressure wave detection technology, which has advantages of short time detection availability, accurate leaking location estimate capability and cost effective, is concentrated in this study. Theoretical analysis of the flow characteristics for leaking through a hole on the pipe wall has been performed by using CFD++, commercial CFD package. The results of 3-dimensional analysis near leaking hole confirm the occurrence of negative pressure wave and verify the characteristics of propagation of the wave which travels with speed equal to the speed of sound in the pipeline contents. For the application of long pipe line system. The method of 1-dimensional analysis has been suggested and verified with results of CFD++.

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Estimation of Deterioration Assessment for Weighting Factors in Pipes of Water Supply Systems Using Analytic Hierarchy Process (계층적분석과정을 이용한 상수관로의 노후도 평가를 위한 항목별 가중치 산정)

  • Kim, Eung-Seok
    • Journal of the Korean Society of Hazard Mitigation
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    • v.8 no.5
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    • pp.15-21
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    • 2008
  • The purpose of this study is to estimate deterioration assessment for weighting factors in pipe network for which each local selfgovernment takes rehabilitation and replacement work at present time. Deterioic hierarchy process(AHP), calculates the weighting factors. The appropriate marks matrix of sixteen deterioration factors are made for the precise decision standard of pipe condition through the result of this analysis. The marks matrix of sixteen deterioration factors can solve the complicated decision making problems of pipe rehabilitation workration factors in the pipe network might be influenced by local factors, such as province, location, or land use, in water supply systems. In this study, the sixteen deterioration factors are determined suitable for domestic situation based on the pipe deterioration factor data inside and outside of the country. Also, we select persons in charge of calculating the detail weighting factors and do survey about important level of each deterioration factors. Delphi method, a question survey method applying the analyts.

A Study on Adequacy of Pipe Deterioration Evaluation Methods using the Endoscope of Water Distribution Pipe (배수관 내시경 조사를 통한 간접적인 관 노후도 평가방법의 적정성 연구)

  • Choi, Tae Ho;Kang, Sin Jae;Choi, Jae Ho;Koo, Ja Yong
    • Journal of Korean Society of Water and Wastewater
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    • v.26 no.5
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    • pp.669-683
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    • 2012
  • The water supply pipes are buried across wide range of areas, so it is hard to spot them using excavation and takes a large amount of expense. Thus, there is a high risk for direct research and application, accompanying many difficulties in implementation of them. Therefore, it is more economical and convenient to use indirect evaluation variables than direct evaluation of the buried pipes in assessing the degree of pipe deterioration. To assess the degree of pipe deterioration using the indirect evaluation variables, it should be done first to identify how and to what extent they affect the degree of deterioration. This study measured the evaluation variables for pipe deterioration using the pipe endoscope and analyzed the measurement results and the degree of impact on the pipes. In addition, this study attempted to evaluate the adequateness of the pipe deterioration evaluation using the indirect variables based on the analysis results. The evaluation variables measured through the pipe endoscope were the thickness of sediments, size of scale, degree of desquamation and condition of connections. For the indirect evaluation variables, the data such as the property data from GIS pipe network map as well as the material, diameter, age and pipe lining material of the pipe, road type, leakage frequency, average water velocity and water pressure using the leakage repair records was collected. Using the collected data, this study comparatively analyzed the indirect evaluation variables for the degree of pipe deterioration and the results from the pipe endoscope to choose appropriate variables for pipe deterioration evaluation and calculated the weights of the indirect variables on the degree of deterioration. The results showed that the order of the impact of indirect variables on deterioration was pipe age > pipe lining material > road type > leakage frequency > average water velocity with their weights of 0.45, 0.20, 0.15, 0.10, and 0.10, respectively. Conclusively, the results suggest that the measures of sediment thickness, scale size, degree of desquamation and condition of connections are appropriate for the evaluation of pipe deterioration and sufficient for the analysis of the impact of the indirect variables on deterioration.

Demonstration of EPRI CHECWORKS Code to Predict FAC Wear of Secondary System Pipings of a Nuclear Power Plant

  • Lee, Sung-Ho;Seong Jegarl;Chung, Han-Sub
    • Nuclear Engineering and Technology
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    • v.31 no.4
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    • pp.375-384
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    • 1999
  • The credibility of CHECWORKS FAC model analysis was evaluated for plant application in a model plant chosen for demonstration. The operation condition at each pipe component was defined before the wear rate analysis by plant data base, water chemistry analysis, and network flow analysis. The predicted wear was compared with the measured wear for 57 sample components selected from 43 susceptible line groups analysed. The inspected 57 locations represent components of highest predicted wear in each line group. Both absolute value and relative ranking comparisons indicated reasonable correlations between the predicted and the measured values. Four components showed much higher measured wear rates than the predicted ones in the feed water train from main feed water pump discharge to steam generator, probably due to high hydrazine concentration operation the effect of which had not been incorporated into the CHECWORKS model. The measured wear was higher than the predicted one consistently for components with least susceptibility to FAC. It is believed that the conservatism maintained during UT data analysis dominated the measurement accuracy. A great deal of enhancement is anticipated over the current plant pipe management program when a comprehensive plant pipe management program is implemented based on the model analysis.

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determination of Optimum Pipe diameter Using Multi-Stage Iterative Method in Water Distribution system (다단계 반복기법을 이용한 관로시스템의 최적관경 결정)

  • Han, Geon-Yeon;Park, Jae-Hong
    • Journal of Korea Water Resources Association
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    • v.31 no.3
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    • pp.327-335
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    • 1998
  • The distribution network is an essential part of all water supply systems. The cost of this portion of any sizable water supply system may amount to most of the entire cost of the project. This study tried to reduce the cost of the distribution system through optimization in system design. To determine pipe diameter considered in water distribution system design, a iterative procedure linked the flow analysis model and optimization model was used. Linear theory was introduced to analyze flowrate and revised-simplex method based on linear programming is used to optimize pipe diameter. This model was applied to wter distribution system with 22 and 35 pipes, and rapidly determine optimized commercial pipe diameters. Keywords : water distribution system, revised simplex method, optimum pipe diameters.

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THE ANALYTIC ANALYSIS OF THE CORE INJECTION COOLING FLOW RATE FOR EMERGENCY WATER SUPPLY SYSTEM IN HANARO (하나로 비상 보충수 공급계통의 노심 주입 냉각유량 해석)

  • Park Yong-Chul;Kim Bong-Soo;Kim Kyung-Ryun;Wu Jong-Sub
    • 한국전산유체공학회:학술대회논문집
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    • 2005.10a
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    • pp.39-44
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    • 2005
  • In HANARO, a multi-purpose research reactor of 30 MWth, the emergency water supply system consists essentially of an emergency water storage tank located in the level of about thirteen meter (13 m) above the reactor core, a three inch ('3\%') diameter water injection pipe line including injection valves from the tank to the reactor cooling inlet pipe and a test loop to do periodic system performance test. When the water level of the reactor pool comes down to the extremely low due to a loss of reactor pool water accident the emergency water stored in the tank should be fed to the core by the gravity force and at that time the design flow rate is eleven point four kilogram per second (11.4 kg/s). But it is impossible periodically to measure the injection flow rate under the emergency condition because the normal water level should be maintained during the reactor operation. This paper describes a flow network analysis to simulate the flow rate under the emergency condition. As results, it was confirmed through the analysis results that the calculated flow rate agrees with the design requirement under the emergency condition.

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