• 제목/요약/키워드: Steam Pressure

검색결과 900건 처리시간 0.025초

마멸에 의해 손상된 증기발생기 전열관의 파열압력 해석 (Analysis of Burst Pressure for Wear-Damaged Steam Generator Tubes)

  • 신규인;박재학
    • 한국안전학회지
    • /
    • 제18권4호
    • /
    • pp.16-22
    • /
    • 2003
  • Generally the rupture of steam generator tubes proceeds from significant plastic deformation before failure. In this study, the burst pressures of damaged steam generator tubes were calculated from the plastic instability analysis with the finite element method. Two wear types, flat and circumferential types were considered. An equation for the burst pressure was proposed by using the strength reduction factor and the Svensson equation. The analysis results were compared with the experiment data from published references and they showed a good agreement with the experiment data.

ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

  • Takeda, Takeshi
    • Nuclear Engineering and Technology
    • /
    • 제50권6호
    • /
    • pp.981-988
    • /
    • 2018
  • An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water reactor. The relief valve of broken SG opened three times after the start of intact SG secondary-side depressurization as the recovery action. Multi-dimensional phenomena specific to the SGTR accident appeared such as significant thermal stratification in a cold leg in broken loop especially during the operation of high-pressure injection (HPI) system. The RELAP5/MOD3.3 code overpredicted the broken SG secondary-side pressure after the start of the intact SG secondary-side depressurization, and failed to calculate the cold leg fluid temperature in broken loop. The combination of the number of the ruptured SG tubes and the HPI system operation difference was found to significantly affect the primary and SG secondary-side pressures through sensitivity analyses with the RELAP5 code.

증기터빈 익렬유동의 에너지손실에 관한 실험적 연구 (An Experimental Study on Energy Losses in Steam Turbine Cascade Flow)

  • 안형준;권순범
    • 대한기계학회논문집
    • /
    • 제19권11호
    • /
    • pp.3022-3030
    • /
    • 1995
  • The irreversibility of condensation process in the supersonic flow of steam turbine cascade causes the entropy to increase and the total pressure loss to be generated. In the present study, in order to investigate the moist air flow in two dimensional steam turbine cascade made as the configuration of the last stage tip section of the actual steam turbine moving blade, the static and total pressures along suction side of the blade are measured by pressure taps and Pitot tube. The flow field is visualized by a Schlieren system. The effects of stagnation temperature and the degree of supersaturation on energy loss and entropy change in the flow are clearly identified.

증기터빈용 Synchro Clutch Coupling의 진동 특성 (Vibration Characteristics of a Synchro Clutch Coupling for Steam Turbine)

  • 심응구;이태구;문승재;이재헌
    • 플랜트 저널
    • /
    • 제4권3호
    • /
    • pp.66-72
    • /
    • 2008
  • The vibration of steam turbine is caused by Mass unbalance, Shaft misalignment, Oil whip and rubbing etc. But in turbine which is normally operated and maintained, the Mass unbalance component possesses the greatest portion. Our power plant has two steam turbines in capacity of 200 MW and 135 MW respectively and each turbine is supported by 6 journal bearings. However, we had many difficulties because the vibration amplitude of #3 and #4 Bearings was high during the start-up and operation mode change of steam turbine. But, with this study, we completely solved the vibration problem caused by the mass unbalance of #1 steam turbine. Until a recent date, #3 and #4 bearings which support high pressure turbine for #1 steam turbine had shown about $135{\mu}m$ in vibration amplitude (sometimes it increased to $221{\mu}m$ maximum. alarm: 6 mils, trip: 9 mils) at base load. After applying the study, they decreased to about $45{\mu}m$ maximum. It is a result from that we did not change the setting value of bearing alignment and only changed the assembly position of internal parts in Synchro clutch coupling rachet wheel which links between high pressure turbine and low pressure turbine, and increased the internal gap and machining of the Pawl cage surface. In the operation of steam turbine, if the vibration value increases by 1X, we should reduce the vibration of bearing by weight balancing. However, unless the vibration of bearing is declined by the balancing, we will have to disassemble and check the component and find the cause. In this study, we researched the way to lower mass unbalance that is 1X vibration component which has the greatest portion of vibration generated by steam turbine and we got good result by applying the findings of this study.

  • PDF

월성 1호기 계속운전을 위한 증기발생기 열화관리 (Wolsong Unit 1 Steam Generator Aging Management for Continued Operation)

  • 송명호;김홍기;이정민
    • 한국압력기기공학회 논문집
    • /
    • 제6권2호
    • /
    • pp.28-33
    • /
    • 2010
  • As a part of license renewal for the continued operation of Wolsong unit 1, the periodic safety review report was submitted near the end of design lifetime, 2012, and now is under reviewing. Major components of primary system such as pressure tubes, feeder pipes and so on are being replaced and many components of secondary system are also being repaired. So the license renewal of Wolsong unit 1 is expected to be acquired without significant issues. But on the other hand, steam generators of Wolsong unit 1 had the good performance and therefore the replacement and repair for the steam generator are not needed. Recently it is reported that some cracks were detected in a few of european steam generator with Alloy 800 tubes and the cause of cracks was the outer diameter stress corrosion cracking(ODSCC) due to the concentration of chemical impurities on the outer surface of tube. Accordingly the overall review on this issue was performed. The long-term operation is likely to results to form the concentration mechanism for the tube corrosion as the sludge build-up in the secondary side of steam generator and the crack in the crevice between tube and tube-sheet and expansion transitions is apt to be occurred. In this paper, the history of steam generator inspection and operation of Wolsong unit 1 are reviewed and the reliability of steam generator tube is evaluated and the steam generator aging management program for Wolsong unit 1 is introduced.

  • PDF

증기압력 변화에 따른 증기 이젝터의 성능에 관한 연구 (A Study on the Performance of Steam Ejector by Variation of Steam Pressure)

  • 전유신;신유식;;정효민;정한식
    • 대한설비공학회:학술대회논문집
    • /
    • 대한설비공학회 2006년도 하계학술발표대회 논문집
    • /
    • pp.761-766
    • /
    • 2006
  • This paper describes a study on the performance of steam ejector by variation of steam pressure. Water temperature is especially important for good qualify of fish in an inland aquafam. In summer season, the water temperature increases above $25^{\circ}C$, but for good quality breeding or fish is the maintenance of optimum aquafam temperature by about $20^{\circ}C$. Therefore it is needed to drop the water temperature to provide suitable conditions of fish growth. There are many kinds of cooling system, in this study using steam ejector. After cooling the water in vacuum tank with the steam ejector then circulate this water to inland aquafam. In this way to minimizes fish stress that it is caused by water temperature. The objective of research confirms the difference of the case which there is no water in the vacuum tank and has water in the vacuum tank. The purpose of this paper is to examine the effects on the performance of steam ejector by variation of steam pressure.

  • PDF

고온 수증기 환경에서 Ni기 초합금의 산화특성 (Oxidation Behaviors of Nickel-Base Superalloys in High Temperature Steam Environments)

  • 김동훈;구자현;김대종;유영성;장창희
    • 한국압력기기공학회 논문집
    • /
    • 제7권2호
    • /
    • pp.26-33
    • /
    • 2011
  • To evaluate steam oxidation behaviours of Alloy 617 and Haynes 230, oxidation test were performed at $900^{\circ}C$ in steam and $steam+20\;vol.-%\;H_2$ environments. Oxidation rate in steam condition was similar to that in air for Alloy 617, while it was slightly lower for Haynes 230. When hydrogen was added to steam, oxidation rate was enhanced. Isolated $MnTiO_3$ particle were formed on $Cr_2O_3$ oxide layer and sub layer $Cr_2O_3$ were formed in steam and $steam+20\;vol.-%\;H_2$ for Alloy 617. On the other hands, $MnCr_2O_3$ layer were formed on top of $Cr_2O_3$ oxide layer for Haynes 230. The extensive sub layer $Cr_2O_3$ formation was resulted from the oxygen inward diffusion in such environments. When hydrogen was added, the oxide morphology was changed from polygonal to platelet because of the accelerated diffusion of cations under the oxide layer. In addition, decarburized zone was extended as hydrogen participated into the reactions causing carbide dissolution.

AN EVALUATION OF THE APERIODIC AND FLUCTUATING INSTABILITIES FOR THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN INTEGRAL REACTOR

  • Kang Han-Ok;Lee Yong-Ho;Yoon Ju-Hyeon
    • Nuclear Engineering and Technology
    • /
    • 제38권4호
    • /
    • pp.343-352
    • /
    • 2006
  • Convenient analytical tools for evaluation of the aperiodic and the fluctuating instabilities of the passive residual heat removal system (PRHRS) of an integral reactor are developed and results are discussed from the viewpoint of the system design. First, a static model for the aperiodic instability using the system hydraulic loss relation and the downcomer feedwater heating equations is developed. The calculated hydraulic relation between the pressure drop and the feedwater flow rate shows that several static states can exist with various numbers of water-mode feedwater module pipes. It is shown that the most probable state can exist by basic physical reasoning, that there is no flow rate through the steam-mode feedwater module pipes. Second, a dynamic model for the fluctuating instability due to steam generation retardation in the steam generator and the dynamic interaction of two compressible volumes, that is, the steam volume of the main steam pipe lines and the gas volume of the compensating tank is formulated and the D-decomposition method is applied after linearization of the governing equations. The results show that the PRHRS becomes stabilized with a smaller volume compensating tank, a larger volume steam space and higher hydraulic resistance of the path $a_{ct}$. Increasing the operating steam pressure has a stabilizing effect. The analytical model and the results obtained from this study will be utilized for PRHRS performance improvement.

증기터빈의 가변패킹 형태에 따른 터빈성능 평가에 관한 연구 (A Study on the Turbine Performance in the steam seal variable clearance packing type of Steam turbine)

  • 권영수;서정세
    • 대한기계학회:학술대회논문집
    • /
    • 대한기계학회 2004년도 추계학술대회
    • /
    • pp.1676-1681
    • /
    • 2004
  • The main reason for applying positive pressure variable clearance packing in fossil power plant is high efficiency and energy saving movement in the government. This study intends to analyze the turbine efficiency through the shaft packing improvement in thermal power plant and makes its comparison to that of the each packing type

  • PDF

에너지절감을 위한 폐열회수용 열압축기에 대한 고찰 (A study for steam energy savings by the thermal vapor recompressor)

  • 이재근
    • 기술사
    • /
    • 제41권3호
    • /
    • pp.50-54
    • /
    • 2008
  • Recently most companies require various type of energy sources, in order to be more energy efficient in their plant due to the increasing current oil price. So, the multi-national companies are shaping ideas how to reduce energy costs and use substitute energy. The purpose of this study Is to attempt to save energy by making more valuable high pressure steam through TVR(Thermal Vapor Recompressor) from the surplus low pressure steam of HRB(Heat Recovery Boiler) in sulfuric acid plant.

  • PDF