• 제목/요약/키워드: Steam Plant

검색결과 943건 처리시간 0.032초

증기연계 공정을 가지는 석탄가스화 복합발전플랜트의 성능해석 (Performance Analysis of the Integrated Gasification Combined Cycle Power Plant with Steam Integration)

  • 이찬
    • 한국유체기계학회 논문집
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    • 제12권1호
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    • pp.43-50
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    • 2009
  • Waste heat recovery process designs and performance analyses are conducted on the IGCC(Integrated Gasification Combined Cycle) power plants integrated with two different coal gasification and gas cleanup processes by Shell and GE/Texaco. Through the analysis results, the present study provides the steam integration concept between the HRSG and the chemical processes of IGCC power plant, and investigates the effect of steam integration on the power generation of IGCC power plant. The present simulation results show less steam power output and higher overall IGCC efficiency of the Shell-based power plant than the GE/Texaco.

울진1,2호기 출력최적화 및 증기발생기 교체가 주급수 제어계통 안정도에 미치는 영향연구 (Research on a Stability of Feedwater Control System after Stretched Power Uprate and Replacement Steam Generator for Ulchin Units 1&2)

  • 윤덕주;김인환;이재용
    • 한국압력기기공학회 논문집
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    • 제8권2호
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    • pp.14-20
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    • 2012
  • Full load rejection capability of nuclear power plant depends primarily on steam dump capacity (SDCAP) and steam generator level control capability. Recently, Ulchin Units 1&2 have performed stretched power uprate (SPU) and replacement steam generator (RSG) projects, which increase the power by 4.5 percent. They change major design or operating parameters and especially reduces steam dump capacity at full power due to increase of the steam flow. The reduction of SDC after SPU results in degradation of heat removal capability in full load rejection transients. Therefore, we should perform evaluation to determine whether reactor trips occur in large load rejection transients. Uchin Units 1&2 have experienced full load rejection (FLR) three times from 2004 to 2010. Operating data from the plant occurrence of FLR at Ulchin Units 1&2 showed that steam generator (SG) level transients were limiting in point of reactor trip. However the plant had never reached reactor trip in the FLR and successfully continued in house load operation. The parameters and setpoints for the SG will be changed if the SG is replaced. Therefore, we evaluated the appropriateness of steam dump, main feedwater and steam generator water level control system preventing the plant from reactor trip in case of FLR by the parameter sensitivity study whether SG water level operated smoothly after SPU and RSG projects.

원자력발전소 증기터빈 발전기의 부하차단 모의시험 (A simulation test of lone rejection for steam turbine generator in nuclear power plant)

  • 최인규;정태원;이기성
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2003년도 하계학술대회 논문집 D
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    • pp.2301-2303
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    • 2003
  • A steam turnine in thermal/nuclear power plant drives generator and maintains it at rated speed using high temperature and high pressure steam energy. After synchronization in parallel with the power system, generator output increases according as the governor, that is the controller, increases steam flow into turbine. By the way, as the steam flow into turbine can not be reduced fast even though the electrical load is lost, the turbine gets into dangerous situation due to the increase of its speed. At this time, the duty of the turbine governor is to limit the speed to its overspeed trip setpoint by stopping the steam flow as soon as possible, the test of which is called load rejection test. It is introduced in this paper for a simulation test of generator load rejection to be implemented on the turbine governor in a 600MW nuclear power plant before its startup.

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수압구동 전열관다발 부분 삽입형 증기발생기 세정장비 설계 (Design of a Partial Inter-tube Lancing System actuated by hydraulic power for type F model Steam Generator in Nuclear Power Plant)

  • 김석태;정우태
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.1132-1135
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    • 2008
  • The sludge grown up in steam generators of nuclear power plants shortens the life-cycle of steam generators and reduces the output of power plants. So KHNP(Korea Hydro and Nuclear Power), the only nuclear power utility in Korea, removes it periodically using a steam generator lancing system during the outage of plants for an overhaul. KEPRI(Korea Electric Power Research Institute) has developed lancing systems with high pressured water nozzle for steam generators of nuclear power plants since 2001. In this paper, the design of a partial inter-tube lancing system for model F type steam generators will be described. The system is actuated without a DC motor inner steam generators because the motors in a steam generator make a trouble from high intensity of radioactivity as a break down.

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대형 터어빈계통의 고효율 배압시스템 개발에 관한 연구(I) (A Study on the Vacuum System for High Efficiency Marine Steam Turbine System)

  • 김경근;윤석환;김용모;김종헌;김철환
    • Journal of Advanced Marine Engineering and Technology
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    • 제18권4호
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    • pp.13-24
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    • 1994
  • The demand of clean energy, like liquefied gas(LNG), increase suddenly because it generates few polluting substances when burned and from the point of view with caloric value it generates ralatively less $CO_2$ gas than the other energy sources. LNG transpotion method of our country is marine transportion by ships because the LNG producing district is far away from Korea. Main engines for most LNG ships are steam turbines, and the efficiency of steam turbine is influenced by the degree of vacuum of main steam condenser. This paper introduce the design method of the vacuum system for high efficiency marine steam turbine. Especially, it is developed the CAD program for the large steam condenser and steam ejector. Also, it is designed the pilot plant including high pressure boiler for the performance test and maked a part of this plant.

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원자력 발전소용 대형 튜브시트 단강품의 개발 (Development of the Large Tubesheet Forgings for Nuclear Power Plant)

  • 김동권;김영득;김동영
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2006년도 춘계학술대회 논문집
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    • pp.176-179
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    • 2006
  • Large tubesheet forgings of the steam generator for the 1,400MW nuclear power plant has been developed. Steam Generator is one of the most important structural part for 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 forging process development 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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화력발전소에서 응축수 회수계통의 증기배관 개선에 의한 발전시스템의 효율 향상 (The improvement of the efficiency of power plant by the reformation of steam line in the return system)

  • 권영수;서정세
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2001년도 추계학술대회논문집B
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    • pp.867-871
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    • 2001
  • The main reason for reviewing the condensate water return system in the auxiliary steam system is to obtain the thermal high efficiency of the power plant and thus save the fossil energy in power plant. This study intends to analyze the thermal efficiency of the power plant and predict the increasing in the generator output by the return system reformation of auxiliary steam line in the thermal power plant.

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증기 원동소의 엑서지 손실에 관한 연구 (A Study on the Exergy Losses of Steam Power Plant)

  • 박재철;장문석;이창식
    • 설비공학논문집
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    • 제1권3호
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    • pp.235-243
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    • 1989
  • The purpose of this paper is to obtain enthalpy balance and exergy analysis for the energy losses in a steam power plant. The enthalpy and exergy analysis of the steam power plant were carried out on the various output of steam turbine. While enthalpy analysis shows that circulating loss in the condenser is maximum, exergy evaluation of the power plant shows that the losses of the boiler and turbine are considerably larger than those of condenser and feed water heater. Most irreversible losses of the power plant occur at the boiler. For improving the performance, the precise study about the irreversible losses of the boiler is necessary.

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지하자원개발을 위한 오일샌드플랜트의 DCSG 증기생산효율 평가에 관한 연구 (A Study on the Evaluation of DCSG Steam Efficiency of Oil Sand Plants for Underground Resources Development)

  • 김영배;정기진;정우현;정석우
    • 한국지열·수열에너지학회논문집
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    • 제18권4호
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    • pp.12-21
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    • 2022
  • Steam assisted gravity drainage(SAGD) is a process that drills well in the underground oil sands layer, injects hightemperature steam, lowers the viscosity of buried bitumen, and recovers it to the ground. Recently, direct contact steam generator(DCSG) is being developed to maximize steam efficiency for SAGD process. The DCSG requires high technology to achieve pressurized combustion and steam generation in accordance with underground pressurized conditions. Therefore, it is necessary to develop a combustion technology that can control the heat load and exhaust gas composition. In this study, process analysis of high-pressurized DCSG was conducted to apply oxygen enrichment technology in which nitrogen of the air was partially removed for increasing steam production and reducing fuel consumption. As the process analysis conditions, methane as the fuel and normal air or oxygen enriched air as the oxidizing agent were applied to high-pressurized DCSG process model. A simple combustion reaction program was used to calculate the property variations for combustion temperature, steam ratio and residual heat in exhaust gas. As a major results, the steam production efficiency of DCSG using the pure oxygen was about 6% higher than that of the normal air due to the reducing nitrogen in the air. The results of this study will be used as operating data to test the demonstration device.

증기터빈의 오일 휩 현상 및 대책

  • 구재량
    • 열병합발전
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    • 통권37호
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    • pp.18-21
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    • 2004
  • There are several bearing system at large steam-turbines in thermal power plant. The bearing system is one of the most important parts of rotating machinery. The steam turbine vibrations mainly depend on the bearing oil the shaft alignment condition. This paper describes on the steam turbine abnormal vibration due to the oil whip in terms of the shaft alignment in the thermal power plant.

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