• Title/Summary/Keyword: Pipe Network Analysis

검색결과 154건 처리시간 0.032초

정압기 임계유동특성 및 배관망해석 요소로서의 고려에 관한 수치해석적 연구(II);단면적 및 개도 변화 (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)

  • 신창훈;하종만;이철구;허재영;임지현;주원구
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2004년도 추계학술대회
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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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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) (Comparison of the Node Method and the Pipeline Method for the Analysis of Water Distribution Systems)

  • 이상목;류종현;현인환
    • 상하수도학회지
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    • 제10권4호
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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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    • 제52권1호
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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.

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

  • 하태웅;하종만;김동혁;김영남
    • 한국가스학회지
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    • 제11권4호
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    • pp.47-53
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    • 2007
  • 고압 가스 배관망의 안전관리는 매우 중요한 문제로 배관의 외적 손상으로 구멍이 생길 경우 발생하는 누출은 폭발 및 환경오염을 포함한 막대한 경제적 손실을 야기할 수 있다. 누출 검지를 위한 PLDS(Pipeline leak detection system린 기술로 저압확장파 검지 기술이 적용되고 있으며 본 논문에서는 CFD++ 상용코드를 활용하여 배관 누출시 유동특성을 이론적으로 해석하여 저압확장파의 발생 메커니즘과 음속으로 확장되는 전파특성을 규명하였다. 또한 긴 배관망에 적용하기 위한 1차원 해석 방법을 제시하고 신뢰성을 CFD해석 결과로 검증하였다.

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

  • 김응석
    • 한국방재학회 논문집
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    • 제8권5호
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    • pp.15-21
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    • 2008
  • 본 연구의 목적은 현재 지방자치단체에서 수행하는 상수관로 개량 및 교체 사업시 상수관로의 노후도 평가를 위한 항목별 가중치를 산정하는 것이다. 상수도시스템에 상수관로의 노후도 항목은 지역 및 위치, 토지이용 등의 특성에 영향을 받을 수 있다. 본 연구에서는 국내외 자료를 바탕으로 국내 실정에 맞는 노후도 항목 16개를 선정하였다. 또한, 노후도 항목별 세분화된 가중치 산정을 위해 실무업체를 선정하여 해당 전문가들을 대상으로 노후도 항목별 중요도에 대한 설문을 실시하였다. 설문 조사 방법으로는 델피법을 이용하여 이 결과를 바탕으로 계층적분석과정(AHP)을 적용하여 노후항목별 가중치를 산정하였다. 분석결과 국내 실무에 적합한 16개 결함항목별 점수배점표를 작성하여 명확한 판단기준을 마련하였으며 관거 개량사업에 있어서 복잡한 의사결정 문제들에 대한 활용 가능성을 제시하였다.

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

  • 최태호;강신재;최재호;구자용
    • 상하수도학회지
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    • 제26권5호
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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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    • 제31권4호
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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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다단계 반복기법을 이용한 관로시스템의 최적관경 결정 (determination of Optimum Pipe diameter Using Multi-Stage Iterative Method in Water Distribution system)

  • 한건연;박재홍
    • 한국수자원학회논문집
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    • 제31권3호
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    • pp.327-335
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    • 1998
  • 상수관망은 상수공급시스템에서 핵심적인 부분이다. 주어진 상수공급시스템에서 배수관망에 대한 비용은 사업전체 비용에 대한 대부분을 차지하고 있다. 관망에 대한 설계과정 중에서 최적화기법을 사용하여 비용을 절감하기 위한 연구가 시도되었다. 주어진 상수관망 시스템의 설계시 고려되는 관경의 결정을 위해 유량해석과 최적화 기법이 연계되어 해석하는 반복기법이 적용되었다. 유량해석을 위해서 선형화기법이 되입되었고 관경의 최적화를 위해서 선형계획법에 기초한 개정 단체법을 이용하였다. 22개 관로와 35개 관로를 가진 실제관망에 본 모형을 적용한 결과 짧은 계산시간으로 최적화된 상용관을 결정할 수 있었다.

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

  • 박용철;김봉수;김경연;우종섭
    • 한국전산유체공학회:학술대회논문집
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    • 한국전산유체공학회 2005년도 추계 학술대회논문집
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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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