• 제목/요약/키워드: hydraulic power plant

검색결과 243건 처리시간 0.034초

가청화를 이용한 댐 수차 발전기소음의 저감효과 평가 (Evaluation on Reduction Effect about Noise of Hydraulic Turbine Dynamo in Dam using Auralization)

  • 설수환;주덕훈;김재수
    • 설비공학논문집
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    • 제20권6호
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    • pp.400-408
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    • 2008
  • Multipurpose Dam, it produces electric energy by converting the potential energy into kinetic energy utilizing its head and quantity of the water. However, in this process, since during the time when the turbine connected to the hydraulic turbine generator revolves, there occurs a ceaseless loud noise, and due to this condition, it is true state that those people who work at inside of the power plant are damaging as hard as they are unable to concentrate on their work. Not only this, because the hydro-electric power generator room that locates at middle section between the hydraulic turbine room and the office is very large space volume, also since it was constructed chiefly by the reflecting material, it is functioning of amplify the noise when operating the generator, the soundproof measure against this condition is necessitated. On such viewpoint, I have presented the problem point of the relevant Hydraulic turbine dynamo and Hydraulic turbine dynamo room, and after improve such problem point, this study has ever investigated the satisfying degree about the noise-reduction at before and after of the improvement of soundproof measure, using the Auralizational technique that can experience virtual acoustic field. It is considering that such result could be utilized usefully as the fundamental material hereafter for the acoustic performance of the hydro-electric power generator room in dam and when its construction.

발전소 수중방류구조 내 수평유공판 설치에 따른 거품발생 저감효과에 관한 실험적 연구 (Experimental Investigation on the Efficiency of Reducing Air Bubble Formation by Installing Horizontal Porous Plate in the Submerged Outlet Structure of Power Plant)

  • 오상호;오영민;강금석;김지영
    • 한국해안·해양공학회논문집
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    • 제20권5호
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    • pp.472-481
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    • 2008
  • 이 연구에서는 보령화력발전소 방수로 수중방류구조에 대한 수리모형실험을 수행하여 수중방류구조 내 흐름 특성을 고찰하고, 수평 유공판 설치에 따른 거품저감 효과를 검토하였다. 수중방류구조 내 단면평균유속은 설계시 거품의 외해 유출 방지를 위해 고려한 목표값 1 m/s 이내에 분포하였다. 또한, 수중방류구조 내 2차 낙하 위치에 수평 유공판을 설치함에 따라 거품의 수중 최대관입깊이가 30~50% 감소함을 확인하였다. 특히, 2차 낙하 위치에 구멍의 크기가 20 cm 정도인 사각구멍형 유공판을 설치하고, 중앙부는 무공 구조로 제작하여 낙하 에너지를 소산시키게 될 경우, 가장 효과적으로 수중에 관입되는 거품 발생량을 저감시킬 수 있을 것으로 기대된다.

표준형 발전소용 터빈 밸브 작동기 성능 분석 시스템 개발 (The development of turbine valve actuator efficiency analysis system for the standard power plants)

  • 노재희;김상협;이동일;양천규;신을영;정재원
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2002년도 합동 추계학술대회 논문집 정보 및 제어부문
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    • pp.537-541
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    • 2002
  • This paper is about the development of the turbine valve actuator efficiency analysis system for the standard power plants. We developed hydraulic power unit and turbine valve actuator controller. We designed control algorithm for turbine valve actuator, implemented and verified it at the industrial plants.

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대형 튜브시트 단강품의 자유단조 (Open Die Forging of Steel Forgings for the Large Tubesheet)

  • 김동권;김재철;김영득;김동영;김정태
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2004년도 추계학술대회논문집
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    • pp.333-337
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    • 2004
  • Steam Generator is one of the most important structural part of nuclear power plant. It is manufactured by various steel forgings such as shell, head, torus and tubesheet. These steel forgings have been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the open die forging process and manufacturing experience of large tubesheet forgings which will be used for the steam generator of 1,400MW nuclear power plant.

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원자로용 대형 헤드 단강품의 자유단조 (Open Die Forging of the Large Head Forgings for Reactor Vessel)

  • 김동영;김영득;김동권
    • 소성∙가공
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    • 제14권6호
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    • pp.565-569
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    • 2005
  • Reactor Vessel is one of the most important structural parts of nuclear power plant. It is manufactured by various steel forgings such as shell, head and transition ring. Head forgings have been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the open die forging process and manufacturing experience of large head forgings which can be used for the reactor vessel of 1,000MW nuclear power plant.

원자로용 대형 헤드 단강품의 개발동향 (Development Trend of the Large Head Forgings for Reactor Vessel)

  • 김동권;김동영;김영득
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2005년도 제10회 단조 심포지엄
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    • pp.131-139
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    • 2005
  • Reactor Vessel is one of the most important structural part of nuclear power plant. It is manufactured by various steel forgings such as shell, head and transition ring. Head forgings has been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the development trend of the open die forging process and manufacturing experience of large head forgings which canl be used for the reactor vessel of nuclear power plant.

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원자로용 대형 헤드 단강품의 자유단조 (Open Die Forging of the Large Head Forgings for Reactor Vessel)

  • 김동영;김영득;김동권
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2005년도 춘계학술대회 논문집
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    • pp.397-400
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    • 2005
  • Reactor Vessel is one of the most important structural part of nuclear power plant. It is manufactured by various steel forgings such as shell, head and transition ring. Head forgings has been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the open die forging process and manufacturing experience of large head forgings which cant be used for the reactor vessel of 1,000MW nuclear power plant.

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Sensitivity analysis of thermal-hydraulic parameters to study the corrosion intensity in nuclear power plant steam generators

  • Tashakor, S.;Afsari, A.;Hashemi-Tilehnoee, M.
    • Nuclear Engineering and Technology
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    • 제51권2호
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    • pp.394-401
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    • 2019
  • The failure of steam generators (SGs) due to corrosion is one of the most important problems in power plants. Impurities usually accumulate in the hot sides of SG and form deposits on the SG surfaces. In this paper, the sensitivity analysis of the accumulation of water impurities in the heat exchangers of nuclear power plants is presented. The convection-diffusion equation of the liquid phase on the heated surfaces is derived and then solved by the finite volume method. Also, the effects of the thermal-hydraulic parameters in the form of dimensionless numbers, such as $Pe_q$, $Pe_u$, $k_q$(relative solubility of impurity between the steam and water) on the impurities concentration are studied.

Robust Force Control of Electro-hydraulic Manipulator in the Field Task

  • Cho, Yong-Rae;Ahn, Kyoung-Kwan;Yang, Soon-Yong;Lee, Byung-Ryong
    • 제어로봇시스템학회:학술대회논문집
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    • 제어로봇시스템학회 2001년도 ICCAS
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    • pp.134.4-134
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    • 2001
  • Hydraulically driven manipulators are superior to electrically driven ones in the power density and electrical insulation. But an electro-hydraulic manipulator using hydraulic actuators has many nonlinear elements, and its parameter fluctuations are greater than those of electrically driven manipulator. So it is relatively difficult to realize not only stable contact work but also accurate force control for the autonomous field tasks such as the maintenance task of high voltage active electric line or the automatic excavation task by hydraulic excavator. In this report, we propose robust force control algorithm, which can be applied to the real field task such as the construction field, nuclear plant and so on. Proposed force controller has the same structure as that of disturbance observer for position control. The difference between force and position disturbance ...

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증기발생기 세관 수압확관부 비파괴검사 방법론 (Methodology of Non-Destructive Examinations on Hydraulic Expansion Region of Steam Generator Tubes)

  • 김창수;정남두;이상훈
    • 한국압력기기공학회 논문집
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    • 제4권2호
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    • pp.29-33
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    • 2008
  • As the measures of nuclear power plant utilities and manufacturers to reduce the defects of tube expansion region during manufacturing steam generators, many types of NDEs(Non-Destructive Examinations) are conducted to inspect the expansion region. The expansion region of tube is subject to degrade because of stress concentration induced by tube expansion, sludge pile and high temperature. So the inspections for tube expansion region have been reinforced. Liquid penetrant test, helium leak test, Bobbin profile test and hydraulic test are performed to confirm the integrity of tube expanded by hydraulic expansion method. Liquid penetrant test and helium leak test are used to inspect seal weld region on tubesheet end part. Bobbin Profile test is used to inspect fully the expanded region of steam generator tube. Hydraulic test finally verifies the integrity of seal weld region on tubesheet end part.

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