• Title/Summary/Keyword: 배관가압

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Prevention of Soil Contamination from Underground Storage Facilities of Petroleum Product and Hazardous Chemical Compounds (유류 및 유해화학물질 저장시설에서의 토양오염 방지대책)

  • 배우근;홍종철;정진욱;김종호
    • Journal of Soil and Groundwater Environment
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    • v.7 no.4
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    • pp.40-47
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    • 2002
  • The practices of the construction and management of the petroleum and hazardous chemical compound storage facilities in Korea were investigated extensively, and the problems were identified. The advanced technologies in the U.S.A were comparatively studied. Considering the effectiveness of leak prevention and applicability, the following measures were suggested. To prevent corrosion of a tank, a clad tank, an interior lining tank, or a double-wall tank were thought to be the most cost effective. For piping. use of non-metalic materials was suggested. A catchment basin seemed to be effective for preventing spills. For monitoring of leaks, constructions of more than one of detection systems, such as an automatic leak detection device. a vapor detection system, a groundwater monitoring system, or a double-wall monitoring system, were recommended.

터보펌프식 액체 로켓의 추진제 공급시스템 설계

  • 조기주;이한주;정영석;임석희;김지훈;오승협
    • Bulletin of the Korean Space Science Society
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    • 2003.10a
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    • pp.89-89
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    • 2003
  • 로켓엔진의 연소에 필요한 추진제를 안정적으로 공급하기 위한 추진제 공급시스템의 주요 구성과 설계 주요 인자를 정리하였다 공급시스템은 추진제 주입/배출 장치, 추진제탱크 가압 및 배기 장치, 추진제 공급 주/분기 배관, 극저온 산화제 온도 유지 장치 등으로 구성되어 있다. 주요 설계 제한 조건으로는 터보 펌프 입구에서의 추진제 압력 및 온도, 필요 추진제 공급 유량 및 온도 그리고 추진제 충진 및 비상 배출 허용 시간 등이며 이는 각 로켓의 해당 임무에 따라 적절히 결정된다. 발사체로부터 할당된 중량값 이내에서 고신뢰도의 작동성, 안정성이 보장되는 시스템을 설계하여야 하며 초기 설계 단계에서 개발 및 수급 가능성을 동시에 고려하여야 할 것이다. 또한 고추력 생성을 위해 엔진 클러스터링이 수행되어야 할 경우 각 엔진으로의 균등한 추진제 배분 공급이 설계의 중요한 요구 조건이 된다. 이러한 공급시스템의 개념은 액체산소와 케로신 조합의 액체 로켓인 100kg급 소형 위성 발사체(KSLV-Ⅰ)에 적용될 예정이다.

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An Optimal Design of Paddy Irrigation Water Distribution System (논관개용 관수로시스템의 최적설계)

  • 안태진;박정응
    • Water for future
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    • v.27 no.4
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    • pp.161-171
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    • 1994
  • The water distribution system problem consists of finding a minimum cost system design subject to hydraulic and operation constraints. The design of new branching network in a paddy irrigation system is presented here. The program based on the linear programming formulation is aimed at finding the optimal economical combination of two main factors: the capital cost of pipe network and the energy cost. Two loading conditions and booster pumps for design of pipe network are considered to obtain the least cost design.

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Experimental Study on the Thermal Flow Stratification in a Horizontal Piping System (수평배관에서의 열유동 성층화현상에 대한 실험적 연구)

  • 김병주;이찬우;장원표
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.19 no.8
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    • pp.2064-2070
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    • 1995
  • Characteristics of thermal flow stratification were studied experimentally by using the small scale pressurizer-surge line model. Thermal flow stratifications in the horizontal section of surge line were analyzed by the relation between the maximum temperature difference at any cross section in surge line and the Froude number representing the boundary conditions, i.e., in/out surge flow velocity and temperature difference of system. Thermal flow stratifications in outsurge flow decreased inversely proportional to the Froude number and did not exist for Fr>1. In insurge flow thermal flow stratifications disappeared near Fr=1.5, but resulted in the higher temperature difference than the case of outsurge flow.

일체형 원자로의 안전용기 냉각이 설계에 미치는 영향

  • 서재광;김주평;윤주현;이두정;장문희
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.276-282
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    • 1996
  • 일체형원자로는 노심, 증기발생기, 가압기, 펌프 등 1차측 주기기들을 하나의 압력용기안에 모두 포함하고 있고, 또 1차측 냉각재가 원자로 안에서만 순환하므로 기존의 분리형원자로에 비해 구조특성상 대용량 원자로 냉각재 상실사고(LBLOCA)의 발생 가능성을 원천적으로 제거할 수 있다. 반면 원자로 냉각재의 보충 등을 위한 소형 배관의 파단 가능성은 역시 존재하므로 소용량 원자로 냉각재 상실 사고(SBLOCA)는 여전히 존재한다. 따라서 현재 한국원자력연구소에서 연구 개발중인 중소규모 전력생산 및 열 활용 목적의 일체형 원자로에는, 원자로 압력용기 외부에 별도의 압력용기(안전용기)를 설치하여 SBLOCA시 원자로 압력용기로부터 방출되는 냉각수를 안전 용기내에 보관하도록 함으로써 사고시 외부로의 방사성 물질 유출 가능성을 획기적으로 줄 일수 있는 설계 개념을 도입하고 있다. 본 논문에서는 안전용기의 설계시 효율적인 냉각방식에 대한 열유체 해석적 접근을 시도하였고, 예비개념설계된 일체형 열병합원자로의 설계상의 특징들 및 안전용기 설계시 앞으로의 연구방향 등도 간략히 소개하였다.

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Thermal stratification in a horizontal pipe of pressurizer surge line (가압기밀림관의 수평배관내 열성층유동)

  • Jung, I,S,;Kim, Y.;Youm, H.K.;Park, M.H.
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.20 no.4
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    • pp.1449-1457
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    • 1996
  • In this paper, the unsteady two dimensional model for the thermal stratification in the pressurizer surge line of PWR plant has been proposed to numerically investigate the heat transfer and flow characteristics. The dimensionless governing equations are solved by using the Control Volume Formulation and SIMPLE (Semi-Implicit Method for Pressure Linked Equations) algorithm. The temperature profile of fluids and pipe wall with time are shown when the thermal stratification occurs in the horizontal pipe. The numerical result shows that the maximum dimensionless temperature difference is about O.514 between hot and cold section of pipe wall at dimensionless time 1,632.

IRWST 배관내의 열수력적 현상 모델링

  • 김상녕;김융석;고종현
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05a
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    • pp.596-602
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    • 1998
  • 한국의 차세대 원자로 (Korean Next Generation Reactor; KNGR)에 처음 적용되는 격납건물내에 설치된 재장전수조 (In-Containment Refueling Water Storage Tank; IRWST)는 기존 재장전수조의 기능외에 주입모드에서 재순환 모드를 전환생략, 일차계통으로 방출된 고온, 고압 냉각수의 응축 및 냉각 격납용기 방사능 오염방지, 원자로 동공층수 등 여러 가지 추가 기능을 가진 한층 진보된 설계개념이다. 발전소 천이사고 시 발생하는 Pipe Clearing, 응축진동 현상(Condensation Oscillations), Chugging 등의 열수력 현상들이 방출증기의 유동 및 가속도와 관련해 항력과 응력, 압력진동 등을 일으켜 IRWST 구조물에 영향을 미칠 수 있기 때문에 IRWST를 처음으로 시도하는 우리 나라로서는 이와 관련된 제반현상에 대한 심도 깊은 연구가 요구된다. 따라서 본 연구에서는 원자력 발전소 과도로 인한 가압기 안전밸브(Pressurizer Safety Valve) 또는 안전감압밸브(Safety Depressurization Valve) 작동시 IRWST로 방출되는 유체로 야기되는 하중 예측 모델을 기존의 BWR의 응축수조(suppression Pool)에서 일어나는 각종 현상을 토대로 이론적으로 체계적으로 유도하여 이를 비교, 분석하였다.

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Numerical analysis for mitigating thermal stratification flow of pressurizer surge horizontal pipe by outside heating (가압기 밀림관 수평배관 외부 가열에 의한 열성층 유동 완화 수치해석)

  • Jeong, I.S.;Kim, Y.
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.21 no.5
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    • pp.670-678
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    • 1997
  • A method to mitigate the thermal stratification phenomenon of pressurizer surge line is proposed by heating bottom outside of horizontal pipe. Unsteady two dimensional model has been used to numerically investigate an effect of heating the bottom of pipe. The dimensionless governing equations are solved by using the control volume formulation and SIMPLE algorithm. Temperature and streamline profiles of fluids and pipe walls with time are compared with the previous study result. The numerical result of this study shows that the outside heating can relaxate the thermal stratification flow of the pressurizer surge line. Maximum dimensionless temperature difference between hot and cold sections of the pipe inner wall which causes thermal stratification was reduced from 0.514 to 0.424 at dimensionless time 1, 632 and 1, 500 respectively.

Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant (고리1호기 계통제염을 위한 원자로냉각재내 유동 특성 평가)

  • Kim, Hak Soo;Kim, Cho-Rong
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.3
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    • pp.389-396
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    • 2018
  • The Kori-1 Nuclear Power Plant (NPP), WH 2-Loop Pressurized Water Reactor (PWR) operated for approximately 40 years in Korea, was permanently ceased on June 18, 2017. To reduce worker exposure to radiation by reducing the dose rate in the system before starting main decommissioning activities, the permanently ceased Kori-1 NPP will be subjected to full system decontamination. Generally, the range of system decontamination includes Reactor Pressure Vessels (RPV), Pressurizer (PZR), Steam Generators (SG), Chemical & Volume Control System (CVCS), Residual Heat Removal System (RHRS), and Reactor Coolant System (RCS) piping. In order to decontaminate these systems and equipment in an effective manner, it is necessary to evaluate the influence of the flow characteristics in the RCS during the decontamination period. There are various methods of providing circulating flow rate to the system decontamination. In this paper, the flow characteristics in Kori-1 NPP reactor coolant according to RHR pump operation were evaluated. The evaluation results showed that system decontamination using an RHR pump was not effective at decontamination due first to impurities deposited in piping and equipment, and second to the extreme flow unbalance in the RCS caused deposition of impurities.

A Study on the Performance of COMS CPS during LEOP (천리안 위성의 LEOP기간 동안의 추진계 성능 연구)

  • Chae, Jong-Won;Han, Cho-Young;Yu, Myoung-Jong
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.40 no.3
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    • pp.258-263
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    • 2012
  • In this paper the Chemical Propulsion Subsystem of COMS is briefly explained and some telemetries acquired by a series operations of CPS during the Launch and Early Operation Phase of COMS are presented. The pressure and temperature of pressurant tank telemetries are compared with the results of the developed computer program. The changes in pressure are due to the two major phases. The first one is the initialization phases of CPS composed of the venting phase to vent the helium gas in the pipe network from the downstream of the propellant tanks to the thrusters for safety, the priming phase to fill the vented pipe network with oxidizer and fuel respectively and then the pressurization phase to pressurize the ullage of propellant tank to regulated pressure. And the other is the apogee engine firings in which COMS CPS is in the orbit raising phase to use helium as a pressurant to keep the pressure of propellant tank as the liquid apogee engine get fired until COMS reached to the target orbit. This program can be applicable to prepare basis design data of the next Geostationary Satellite CPS.