• Title/Summary/Keyword: Pressure Vessel Pipe

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A Study on Modeling of the Pneumatic Part in a Gas Blow-Down System Including Pressure Regulator and Pipe-Line Characteristics (압력조절밸브와 배관 특성을 포함한 유도무기용 기체 블로우다운 시스템의 공압부 모델링에 관한 연구)

  • Park, Youngwoo
    • Journal of Drive and Control
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    • v.14 no.3
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    • pp.32-39
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    • 2017
  • In this study, a mathematical model of the pneumatic part in a gas blow-down system is proposed. The mathematical model consists of four major parts: pressure vessel, reservoir, pressure regulator and pipe-line. To ensure accuracy in long-time simulations, heat transfer between gas and pressure vessel is considered. The model is validated by comparing simulation results with experimental data. Experiments are conducted on the ground, where free convection can be assumed. Simulation results indicate the proposed model can accurately describe behavior of a gas blow-down system. Therefore, it may be used for design and analysis of similar systems with a slight modification.

A Study on the Evaluation of Pressure Resistance and Effective Thermal Conductivity of Thin Heat Pipes Using Polymer Compound Sheets for Bonding Metal Thin Plates (금속박판 접합용 고분자화합물시트를 이용한 박형 히트파이프 내압성 및 유효열전도율 평가에 관한 연구)

  • Yu, Byeong-Seok;Kim, Jeong-Hun;Kim, Dong-Gyu
    • Journal of the Korean Society of Industry Convergence
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    • v.24 no.4_2
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    • pp.509-515
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    • 2021
  • In this study, a pressure vessel for a heat pipe was fabricated by bonding a metal thin film using a polymer compound sheet. In order to confirm the applicability of the experimentally manufactured copper material thin heat pipe of 0.6 mm or less, the pressure resistance and effective thermal conductivity for pressure generated according to the type of the working fluid of the heat pipe were evaluated to suggest the commercialization potential of the thin heat pipe. As a result of evaluating the pressure resistance and effective thermal conductivity performance of the thin heat pipe, the following conclusions were drawn. 1) Using a PEEK-based polymer compound sheet, it was possible to fabricate a pressure vessel for a thin heat pipe with a pressure resistance of up to 1.0 MPa by bonding a copper thin film, and the possibility of commercialization was confirmed at a temperature below 120 ℃. 2) In the case of the effective thermal conductivity performance evaluation test, the effective thermal conductivity of ethanol was higher than that of FC72 and Novec7000, and in the case of ethanol, the maximum effective thermal conductivity was 2,851 W/mK at 3.0 W of heating.

Defect Depth Measurement of Straight Pipe Specimen Using Shearography (전단간섭계를 이용한 직관시험편의 결함 깊이 측정)

  • Chang, Ho-Seob;Kim, Kyung-Suk
    • Journal of the Korean Society for Nondestructive Testing
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    • v.32 no.2
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    • pp.170-176
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    • 2012
  • In the nuclear industry, wall thinning defect of straight pipe occur the enormous loss in life evaluation and safety evaluation. To use non-destructive technique, we measure deformation, vibration, defect evaluation. But, this techniques are a weak that is the measurement of the wide area is difficult and the time is caught long. In the secondary side of nuclear power plants mostly used steel pipe, artificiality wall thinning defect make in the side and different thickness make to the each other, wall thinning defect part of deformation measure by using shearography. In addition, optical measurement through deformation, vibration, defect evaluation evaluate pipe and thickness defects of pressure vessel is to evaluate quantitatively. By shearography interferometry to measure the pipe's internal wall thinning defect and the variation of pressure use the proposed technique, the quantitative defect is to evaluate the thickness of the surplus. The amount of deformation use thickness of surplus prediction of the actual thickness defect and approximately 7 percent error by ensure reliability. According to pressure the amount of deformation and the thickness of the surplus through DB construction, nuclear power plant pipe use wall thinning part soundness evaluation. In this study, pressure vessel of thickness defect measure proposed nuclear pipe of wall thinning defect prediction and integrity assessment technology development. As a basic research defected theory and experiment, pressure vessel of advanced stability and soundness and maintainability is expected to contribute foundation establishment.

Comprehensive Consideration on the Discharge of Gases from Pressurized Vessels through Pressure Relief Devices (압력용기로부터 압력방출장치를 통한 가스 방출에 관한 포괄적 고찰)

  • Chung, Chang-Bock
    • Journal of the Korean Society of Safety
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    • v.35 no.6
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    • pp.32-45
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    • 2020
  • The problem of determining the discharge rates of gases from pressurized vessels through pressure relief devices was dealt with comprehensively. First, starting from basic fluid flow equations, detailed modeling procedures were presented for isentropic nozzle flows and frictional flows in a pipe, respectively. Meanwhile, physical explanations were given to choking phenomena in terms of the acoustic velocity, elucidating the widespread use of Mach numbers in gas flow models. Frictional flows in a pipe were classified into adiabatic, isothermal, and general flows according to the heat transfer situation around the pipe, but the adiabatic flow model was recommended suitable for gas discharge through pressure relief devices. Next, for the isentropic nozzle flow followed by adiabatic frictional flow in the pipe, two equations were established for two unknowns that consist of the Mach numbers at the inlet and outlet of the pipe, respectively. The relationship among the ratio of downstream reservoir pressure to upstream pressure, mass flux, and total frictional loss coefficient was shown in various forms of MATLAB 2-D plot, 3-D surface plot and contour plot. Then, the profiles of gas properties and velocity in the pipe section were traced. A method to quantify the relationship among the pressure head, velocity head, and total friction loss was presented, and was used in inferring that the rapid increase in gas velocity in the region approaching the choked flow at the pipe outlet is attributed to the conversion of internal energy to kinetic energy. Finally, the Levenspiel chart reproduced in this work was compared with the Lapple chart used in API 521 Standatd.

Evaluation of the Corroded Pipe by Time-Frequency Analysis (시간-주파수 해석에 의한 부식된 배관의 평가)

  • Ahn, S.H.;Kim, J.W.;Do, J.Y.;Nam, K.W.
    • Journal of Power System Engineering
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    • v.10 no.2
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    • pp.89-92
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    • 2006
  • In this study, the pressure vessel piping with corrosion used during long term were investigated from the time-frequency analysis method. The damage of piping could be evaluated the attenuation factor by ultrasonic parameters such as center frequency and echo waveform. Based on NDE analysis by time-frequency analysis method, it should also be possible to evaluate from various damages and defects in piping members.

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Comparative Study on Water Hammer for Pump Station in High Pressurized Pipes in Kuwait

  • Shim, Kyu Dae;Kang, Yong Suk;Choung, Joon Yeon;Abdellatif, Mohamed;Kim, Dong Kyun
    • Proceedings of the Korea Water Resources Association Conference
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    • 2017.05a
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    • pp.265-269
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    • 2017
  • Because of abrupt changes for velocity in water, transient flow is occurred in practical life. To reduce and avoid the high or low pressure of pipe network system, various surge protection facilities are used to prevent the risk in pipe network system. Especially, we focused on study not only preventing positive and negative pressure but also selecting adequate equipment for high pressurized pipelines. Several critical cases were considered by undertaking a steady state hydraulic study and transient dynamic simulation and we suggested that the surge vessel of various surge protection system was recommended to control high and low pressures on pipeline system in perspective.

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A study on the Measurement of Internal Defects of Pressure Vessel by using ESPI Methods (ESPI 방법들을 이용한 압력용기 내부 결함 측정에 관한 연구)

  • LEE J.S;Kang Y.J.;Baik S.H.
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2005.06a
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    • pp.1803-1807
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    • 2005
  • The pipe which it uses from the nuclear power plant or factory by a long period use and a corrosive action the inside defect occurs on the inside. abstract here. The ESPI method is in order to investigate the laser light in the measurement object it will be able to measure the wide territory whole in once, does not receive an effect in direction of defect not to be, has the strong point it will be able to measure a change of place arrowhead real-time defect. It measured a inside defect of pressure vessel by using Out of plane ESPI and In plane of ESPI. It compared a each method result.

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A study on the Measurement result comparison of Internal Defects of Pressure Vessel by using ESPI Methods and FEM Methods (ESPI를 이용한 압력용기 내부 결함 측정 결과와 유한 요소 법을 이용한 결과 비교에 관한 연구)

  • Lee J.S.;Kang Y.J.;Baik S.H.
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2005.10a
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    • pp.910-913
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    • 2005
  • The pipe which it uses from the nuclear power plant or factory by a long period use and a corrosive action the inside defect occurs on the inside. abstract here. The ESPI method is in order to investigate the laser light in the measurement object it will be able to measure the wide territory whole in once, does not receive an effect in direction of defect not to be. has the strong point it will be able to measure a change of place arrowhead real-time defect. It measured a inside defect of pressure vessel by using ESPI and FEM. It compared a each method result.

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Development of Stress Indices for Trunnion Pipe Support (원통형 배관 지지대의 응력계수 개발)

  • 김종민;박명규;엄세윤;이대희;박준수
    • Computational Structural Engineering
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    • v.9 no.3
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    • pp.115-123
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    • 1996
  • A finite element analysis of a trunnion pipe anchor is presented. The structure is analyzed for the case of internal pressure and moment loadings. The stress results are categorized into the average (membrance) and the linearly varying(bending) stresses through the thickness. The resulting stresses are interpreted per Section III of the ASME Boiler and Pressure Vessel Code from which the Primary (B/sub 1/) and Secondary(C/sub 1/) stress indices for pressure, the Primary(B/sub 2R/, B/sub 2T/) and Secondary(C/sub 2R/, C/sub 2T/) stress indices for moment are developed. Several analyses were performed for various structural geometries in order to obtain empirical representation for the stress indices in terms of dimensionless ratios.

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Design of Vessel Assembly for Fuel Irradiation Test in Reactor (원자로 내 핵연료조사시험용 압력용기조립체 설계)

  • Park, Kook-Nam;Lee, Jong-Min;Chi, Dae-Young;Park, Su-Ki;Lee, Chung-Young;Kim, Young-Jin
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.383-387
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    • 2004
  • The Fuel Test Loop (FTL) consists of In-Pile Test Section (IPS) and Out-of-Pile System (OPS). The test condition in IPS such as pressure, temperature and quality of the main cooling water, can be controlled by the OPS. The FTL has been developed to be able to irradiate three pins to the core irradiation hole (IR1 hole) by considering for its utility and user's irradiation requirement. The IPS vessel assembly (IVA) consists of IPS head, outer pressure vessel, inner pressure vessel, inner assembly and test fuel carrier. The IVA is approximately 5.6 m long and fits within a 74 mm in diameter envelope over the full height of the chimney. Above the top of the chimney, the head of the IPS is enlarged to allow the closure flanges and pipe work connections. IVA was designed to test the CANDU and PWR nuclear fuel pin together. Specially, wished to minimize interference by nuclear fuel change in design and synthesize these items and shape design for IVA.

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