• Title/Summary/Keyword: 배관 계통

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A Study on the Pressure Drops of T-Branch Pipes (분기배관의 압력강하에 관한 연구)

  • Nam, Jun-Seok;Baek, Chang-Sun;Kwon, Soon-Kwan;Kim, Dong-Hyun;Min, Kyung-Tak;Kim, Byoung-Gon;Lee, Sung-Ho
    • Fire Science and Engineering
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    • v.22 no.3
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    • pp.272-277
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    • 2008
  • This study is performed for propose that exactly equivalent length of TBP in the applied at water-based fire protection system. For predict the measuring position of equivalent length, we determined the measuring position using the FVM about pressure drop of TBP. For the reckon of the exact about measured value we compared with the result of FVM and we knew the similar value each other. Using the results we proposed the friction loss measuring position that inlet of main dirction is 20 times of appellation diameter in main pipe, outlet of main dirction is 10 times of appellation diameter in main pipe and outlet of branched direction is 20 times of appellation diameter.

A Study on the Vibration Reduction Method for Main steam Piping in Nuclear Power Plant (원자력발전소 주증기관의 진동감쇠 연구)

  • Kim, Yeon-Whan;Kim, Jong-Yeob;Lee, Hyun
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 1996.04a
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    • pp.215-220
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    • 1996
  • 원자력발전소의 주증기관은 증기발생기와 터빈을 연결하는 주요 계통으로서 여기서 발생하는 배관진동은 주요기기의 연결부, 밸브, 배관지지물과 건물 등에 복합적인 반복하중을 가하여 관련 지지물 및 구조물에 열화현상을 발생시켜 발전소의 안전운전에 심각한 영향을 초래할 가능성을 항상 내포하고 있다. 그럼에도 불구하고 배관진동 대책은 대부분 지지물을 추가로 설치하여 진동준위만 낮추고 있는 실정이다. 따라서 구체적인 배관진동의 예측, 측정 및 평가, 감쇠방안에 이르는 종합적이고 체계적인 연구가 요구되고 있다. 본 연구에서는 지지물의 열화현상 및 부분적인 파손으로 진동준위가 높아진 것으로 추정되는 원자력발전소 주증기관의 진동특성 및 요인을 분석하여 진동감쇠 방안을 도출하고 검증함으로써 배관 및 주변 구조물의 건전성을 확보하고 설비의 신뢰성을 확보하고자 하였다. 이를 위하여 주증기관을 모델링하여 해석하였으며, 발전소의 기동 및 정상운전시의 진동준위를 측정하였다. 또한 발전소의 정진기간중 일부 배관계에 대한 실험적 모우드 해석을 수행하였다. 여러가지 진동감쇠 방안을 검토하여 탄성지지 및 에너지 흡수효과를 동시에 발휘할 수 있는 특수 지지물(WEAR$_{TM}$)을 설치하는 방안을 도출하였으며, 현장에 설치한 후 배관의 진동상태를 확인함으로서 효과적인 방안임을 검증하였다.

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A Study on System Stress Analysis of High Temperature Plant Piping with Expansion Joints and Load Hangers (신축이음과 하중행거가 함께 설치된 고온플랜트 배관계의 시스템응력 해석 연구)

  • Park, Do Jun;Yu, Jong Min;Han, Seung Yeon;Yoon, Kee Bong;Kim, Ji Yoon
    • Journal of Energy Engineering
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    • v.23 no.3
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    • pp.116-124
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    • 2014
  • In the plants operated under high temperature condition, piping system load analysis is often performed to prevent accidents caused by thermal deformation and also to locate inspection prioritity points of the piping system. In this study, piping system stress analysis was performed for a pipe system between the reactors in a process plant. The piping system includes typically installed hangers and expansion joints. In order to evaluate the effects of structural components such as hangers and expansion joints, the case for the expansion joint or the hanger under abnormal operation is considered. By comparison anlaysis results of piping system during normal operation and abnormal operation, the role of each pipe components are studied.

Risk Assessment Technique for Gas Fuel Supply System of Combined Cycle Power Plants (II) : Based on Piping System Stress Analysis (복합화력발전의 가스연료 공급계통에 대한 위험도 평가 기법 연구 (II) : 배관 시스템 응력 해석을 이용한 위험도 평가)

  • Yu, Jong Min;Song, Jung Soo;Jeong, Tae Min;Lok, Vanno;Yoon, Kee Bong
    • Journal of Energy Engineering
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    • v.27 no.2
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    • pp.14-25
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    • 2018
  • The combined cycle power plant has a cycle of operating the gas turbine with fuel, such as natural gas, and then producing steam using residual heat. The fuel gas is supplied to the gas turbine at a level of 4 to 5 MPa, $200^{\circ}C$ through a compressor and a heat exchanger. In this study, the risk assessment method considering the piping system stress was carried out for safe operation and soundness of the gas fuel supply piping system. The API 580/581 RBI code, which is well known for its risk assessment techniques, is limited to reflect the effect of piping stress on risk. Therefore, the systematic stress of the pipeline is analyzed by using the piping analysis. For the study, the piping system stress analysis was performed using design data of a gas fuel supply piping of a combined cycle power plant. The result of probability of failure evaluated by the API code is compared to the result of stress ratio by piping analysis.

Optimization of pipeline Operation for Stable Landfill Gas Collection Using Numerical Analysis (안정적 매립가스 포집을 위한 배관망 최적운용 분석)

  • 김인기;김세준;허대기;김현태;성원모;배위섭
    • Journal of Soil and Groundwater Environment
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    • v.6 no.3
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    • pp.43-52
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    • 2001
  • It is important that the gas collected from wells completed in waste landfill should be continuously and stably transported to pre-treatment stage through pipelines. The transport is generally affected by fluid flow characteristics of landfill, gas reserves, leachate moisture holdup in pipeline, structures and dimensions of pipeline network, etc. This paper analyzes the pipeline transport and collection mechanism for gas generated in a durable waste landfill. From the results, the optimal controlled scheme of blower inlet pressure is proposed for the prevention of trapped gas pocket zones.

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An Analysis on Thermal Stratification in Residual Heat Removal System Piping of Nuclear Power Plant (가동원전 잔열제거계통 배관에서의 열성층유동 해석)

  • Park, M.H.;Kim, K.C.;Kim, K.H.
    • Proceedings of the KSME Conference
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    • 2003.04a
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    • pp.1597-1602
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    • 2003
  • Numerical analysis is carried out to assess the temperature distribution on the mixing tee line of Residual Heat Removal System (RHRS). In RHRS, hot and cold fluids of main and bypass piping are mixed and unmixed by the flow rate or piping layout. Thermal stratification phenomenon is a cause of major degradation on RHRS piping. According to the analysis for each operation modes, maximum temperature difference between top and bottom of piping were evaluated about 60K when the flow rate of main and bypass lines is same. Temperature difference will be decreased at the elbow on RHRS piping if the length of vertical piping is increased.

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Evaluation the Impact of Installing a Isolation Valve on Condensate System of Nuclear Power Plan (원자력발전소 복수기 수실 차단밸브 설치 영향 평가)

  • Lee, Sun-Ki
    • Journal of Industrial Convergence
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    • v.18 no.4
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    • pp.15-21
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    • 2020
  • Because there are no isolation valves in condensate system of nuclear power plants, circulating water pump was shutdown for the condenser repair. When circulating water pump was shutdown, power plant output decreased about 45%. These output decreasing can minimize by establishing isolation valves. In this paper, evaluated effect to flow conditions change of condensate system, structural integrity of system, condenser pressure of in case of establish isolation valves to condensate system. Results of the evaluation, the flow rate due to the installation of the isolation valve decreased 0.3% when the valve was fully opened and 4.5% when fully closed. In addition, it was found that the vacuum degree of the condenser decreased with decreasing flow rate, but the integrity of the system was maintained.