• Title/Summary/Keyword: 고온 배관

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Development of 3-D. Displacement Measurement System for Critical Pipe of Fossil Power Plant (화력발전소 주배관 3차원 변위측정시스템 개발)

  • Song, G.W.;Hyun, J.S.;Ha, J.S.;Cho, S.Y.
    • Proceedings of the KSME Conference
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    • 2003.11a
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    • pp.1198-1205
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    • 2003
  • Most domestic fossil power plant have exceeded 100,000 hours of operation with the severe operating condition. Among the critical components of fossil power plant, high temperature steam pipe system have had a many problems and damage from unstable displacement behavior because of frequent start up and shut down. In order to prevent the serious damage and failure of the critical pipe system in fossil power plant, 3-dimensional displacement measurement system were developed for the on-line monitoring system. 3-D Measurement system was developed with using the LVDT type sensor and rotary encoder type sensor, this system was installed and operated on the real power plant successfully. In the future time, network system of on-line diagnosis for critical pipe will be designed.

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Identifying Risk Management Locations for Synthetic Natural Gas Plant Using Pipe Stress Analysis and Finite Element Analysis (배관응력해석 및 유한요소해석에 의한 SNG플랜트의 리스크 관리 위치 선정)

  • Erten, Deniz Taygun;Yu, Jong Min;Yoon, Kee Bong;Kim, Ji Yoon
    • Journal of Energy Engineering
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    • v.26 no.2
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    • pp.1-11
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    • 2017
  • While they are becoming more viable, synthetic natural gas (SNG) plants, with their high temperatures and pressures, are still heavily dependent on advancements in the state-of-the-art technologies. However, most of the current work in the literature is focused on optimizing chemical processes and process variables, with little work being done on relevant mechanical damage and maintenance engineering. In this study, a combination of pipe system stress analysis and detailed local stress analysis was implemented to prioritize the inspection locations for main pipes of SNG plant in accordance to ASME B31.3. A pipe system stress analysis was conducted for pre-selecting critical locations by considering design condition and actual operating conditions such as heat-up and cool-down. Identified critical locations were further analyzed using a finite element method to locate specific high-stress points. Resultant stress values met ASME B31.3 code standards for the gasification reactor and lower transition piece (bend Y in Fig.1); however, it is recommended that the vertical displacement of bend Y be restricted more. The results presented here provide valuable information for future risk based maintenance inspection and further safe operation considerations.

고온고압배관의 손상평가 및 실제 사례

  • Ha, Jeong-Su
    • 열병합발전
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    • s.27
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    • pp.5-9
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    • 2002
  • High pressure steam pipe in power plants is subjected to service conditions under which creep processes take place limiting the component's lifetime. To ensure a safe and economic operation it is necessary to get accurate information about the lifetime situation of single components as well as of the whole system. Careful evaluation is combined with FEM analysis, NDT, microstructure evaluation. Especially, 14MoV63 steel is used as material for main steam pipe for 30 years old power plants. In service inspections have shown an increasing number of cracks and creep cavities beside stress concentration parts. A detailed analysis came to the conclusion that lifetime has been consumed to a high degree, 80%level.

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취급제품소개

  • 권태영
    • Proceedings of the Korean Vacuum Society Conference
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    • 2000.02a
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    • pp.39-39
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    • 2000
  • 당사는 1996년 SPUTTERING SYSTEM 제작을 시작으로 하여 진공관련장치 및 부품을 제작, 납품하는 기업입니다. 그 동안 산업체 및 대학, 연구소 등에 제작 납품된 품목은 양산용SPUTTER 연구실험용SPUTTER, ION PLATING, RIE SYSTEM, E-BEAM 증착기 산업용 AL-EVAPORATOR, 산업용 AIP SYSTEM, 고온열처리로, 진공건조장치 진공 배기SYSTEM, 기타 진공관련장치가 있으며 진공부품으로는 OIL ROTARY PUMP, DIFFUSION PUMP, VALVE 및 배관부품 등이 있습니다. 그밖에 취급하는 품목으로는 진공게이지류 및 터보펌프를 판매하고 있습니다. 일부 장치는 기술력을 인정받아 일본, 동남아시아, 중국 등에 수출되었습니다. 당사는 항상 고객이 필요로 하는 진공응용장치를 다년간 축적된 제조기술과 연구력을 바탕으로 만족스러운 제품을 공급하고 있기에 이를 소개하고자 합니다.

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원자로 냉각재배관의 열취화 평가

  • 장윤석;조성빈;진태은;장창희;정일석;홍승열
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.489-494
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    • 1997
  • 주조 스테인레스강으로 제작된 원자로 냉각재배관은 고온에서 장기간 운전됨에 따라 열취화의 영향을 받을 수 있다. 장기간의 열취화는 재료의 연성 및 파괴인성을 저하시킬 수 있으며, 배관에 균열이 존재하는 경우 건전성을 위협할 수 있다. 따라서 본 논문에서는 원전수명연장을 위한 타당성 검토 측면에서 Chopra의 방법 등을 이용한 원자로 냉각재배관의 열취화 평가 및 민감도 분석을 수행하였다. 이를 통해 원자로 냉각재배관의 열취화 수준을 정량화하였고, 건전성 평가에 활용될 수 있는 J$_{IC}$ 값을 예측하였으며, 열취화에 영향을 미치는 주요 인자를 도출하였다.

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ISM에 의한 발전용 고온 배관재료 2.25Cr1Mo강의 고온 크리프 수명 예측에 관한 연구

  • Lee, Sang-Guk;Jeong, Min-Hwa;O, Se-Gyu;Song, Jeong-Geun
    • Journal of Ocean Engineering and Technology
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    • v.12 no.2 s.28
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    • pp.71-78
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    • 1998
  • In this report for the assessment of creep properties of high-temperature tube materials in power plants, the long-time($10^4$~105h) creep life prediction by ISM for 2.25Cr1Mo steel was studied. It was clarified experimentally and quantitatively that the newly developed long-time creep life prediction equation was very coincident with the actual experimental data with high confidence, and the model was $t_r=\alpha\varepsilon_0^{\beta}\sigma^{-1}$.

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Elastic High-temperature Structural Analysis on the Small Scale PHE Prototype Considering the Pipeline Stiffness (배관 강성을 고려한 소형 공정열교환기 시제품에 대한 탄성 고온구조해석)

  • Song, Kee-nam;Kang, J-H;Hong, S-D;Park, H-Y
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.7 no.3
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    • pp.48-53
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    • 2011
  • A PHE (Process Heat Exchanger) is a key component required to transfer heat energy of $950^{\circ}C$ generated in a VHTR (Very High Temperature Reactor) to the chemical reaction that yields a large quantity of hydrogen. A small-scale PHE prototype made of Hastelloy-X is being tested in a small-scale gas loop at Korea Atomic Energy Research Institute. In this study, as a part of the evaluation on the high-temperature structural integrity of the small-scale PHE prototype, we carried out macroscopic high-temperature structural analysis of the small-scale PHE prototype under the gas loop test conditions considering the pipeline stiffness.

Application of Laser-based Ultrasonic Technique for Evaluation of Corrosion and Defects in Pipeline (배관부 부식 및 결함 평가를 위한 레이저 유도 초음파 적용 기술)

  • Choi, Sang-Woo;Lee, Joon-Hyun;Cho, Youn-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.25 no.2
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    • pp.95-102
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    • 2005
  • There are many tube and pipeline in nuclear power plant under high temperature and high pressure. Erosion and corrosion defects were expected on these tube and pipe-line by environmental and mechanical factors. These erosion and corrosion defects ran be evaluated by ultrasonic technique. In these study, Scanning Laser Source(SLS) technique was applied to detect defect and construct image. This technique also makes detection possible on rough and curved surfaces such as tube and pipe-line by scanning. Conventional ultrasonic scanning technique requires immersion of specimen or water jet for transferring ultrasonic wave between transducer and specimen. However, this SLS technique does not need contacting and couplant to generate surface wave and to get flaw images. Therefore, this SLS technique has several advantages, for complicated production inspection, non-contact, remote from specimen, and high resolution. In this study, SLS images were obtained with various conditions of generation laser ultrasound and receiving in order to enhance detectability of flaws on the tube. Stress corrosion cracks were produced on tube and images of stress corrosion cracks were constructed by using SLS technique.

In-Situ Raman Spectroscopic Investigation of Oxide Films on Structural Materials in Nuclear Power Plants (라만 분광법을 이용한 원전 구조재료 실시간 산화막 분석 연구)

  • Kim, Jong Jin;Kim, Ji Hyun
    • CORROSION AND PROTECTION
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    • v.12 no.1
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    • pp.24-29
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    • 2013
  • 원자력 발전소의 설계 수명이 늘어나고 기존의 가동 원전 또한 장기 운전을 목표로함에 따라, 원자로 압력용기, 가압기, 증기발생기, 배관 등의 주요 구조재료의 장기 열화에 따른 재료 건전성을 유지하는 것이 매우 중요하다. 특히, 응력부식균열 현상은 장기 열화에 의해 일어날수 있는 구조재료에서의 심각한 취화 문제들중의 하나로써, 이 현상을 예방하거나 지연시키기 위해서는 현상의 근본원인과 작동기구를 규명하는 것은 원전의 안전성 유지를 위해 매우 중요하다. 이를 위해서 구조재료 표면의 원전 운전 조건에서의 산화막 특성과 그 형성 거동을 분석하는 것은 매우 중요하게 되는데, 원전 운전 조건은 고온고압의 수화학 환경으로 일반 환경에서 사용가능한 다양한 분석 방법들을 적용하기에 많은 제약을 받게 된다. 그러나, 라만 분광법은 가동 원전의 운전 조건인 고온/고압수 환경 하에서도 실시간으로 산화막 분석이 가능한 기법으로, 본 논문에서는 지금까지의 라만 분광법을 이용하여 고온고압수 환경에서의 주요 구조용 금속 및 합금 표면에 생성된 산화막에 대한 분석 연구 결과에 대하여 소개하고, 앞으로 이를 이용한 구조재료의 열화 현상을 분석 및 열화기구 규명을 위한 연구개발 방향을 제시하고자 한다.

Failure Analysis on High Pressure Steam Piping of 500 MW Thermal Power Plant (500 MW 화력발전소 고압 증기 배관 손상 원인 분석)

  • Kim, Jeongmyun;Jeong, Namgeun;Yang, Kyeonghyun;Park, Mingyu;Lee, Jaehong
    • KEPCO Journal on Electric Power and Energy
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    • v.5 no.4
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    • pp.323-330
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    • 2019
  • The 500 MW Korean standard coal-fired power plant is the largest standardized power plant in Korea and has played a pivotal role in domestic power generation for over 20 years. In addition to the aging degradation due to long term operation, the probability of failure of power generation facilities is increasing due to frequent startup and stop caused by the lower utilization rate due to air pollution problem caused by coal-fired power plants. Among them, steam piping plays an important role in transferring high-temperature & pressure steam produced in a boiler to turbine for power generation. In recent years, failure of steam piping of large coal-fired power plant has frequently occurred. Therefore, in this study, failure analysis of high pressure piping weld was conducted. We identify the damage caused by high stress due to abnormal supporting structure of the piping and suggest improved supporting structure to eliminate high stress through microstructure analysis and piping stress analysis to prevent the occurrence of the similar failure of other power plant in the case of repetitive damage to the main steam piping system of the 500 MW Korean standard coal-fired power plant.