• 제목/요약/키워드: high temperature steam

검색결과 560건 처리시간 0.035초

고압형 메탄올 수증기 개질기 압력용기의 내부 유동 개선을 위한 전산 해석 (Computational Analysis for Improving Internal Flow of High Pressure Methanol Steam Reformer Pressure Vessel)

  • 유동진;지현진;유상석
    • 한국수소및신에너지학회논문집
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    • 제31권5호
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    • pp.411-418
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    • 2020
  • A reformer is a device for producing hydrogen used in fuel cells. Among them, methanol steam reformer uses methanol as fuel, which is present as a liquid at room temperature. It has the advantage of low operating temperature, high energy density, and high hydrogen production. The purpose of this study is to improve the internal flow of the pressure vessel when a bundle of methanol steam reformer in the pressure vessel goes out to a single outlet. An analysis of equilibrium reaction to methanol steam reforming reaction was conducted using Aspen HYSYS® (Aspen Technology Inc., Bedford, USA), and based on the results, computational analysis was conducted using ANSYS Fluent® (ANSYS, Inc., Canonsburg, USA). For comparison of the results, the height of the pressure vessel, outlet diameter, and fillet was set as variables, and the optimum geometry was selected by comparing the effects of gravity and the amount of negative pressure.

500 MW급 텐덤형 스팀 터빈 로터의 고온 열화평가 (Evaluation of the High Temperature Degradation of the Rotor of a 500 MW Tandem Steam Turbine)

  • 구대환;유호선;문승재
    • 플랜트 저널
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    • 제10권1호
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    • pp.40-46
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    • 2014
  • 500 MW급 석탄화력발전소인 당진화력 4호기 텐덤형 증기 터빈 로터의 고온부위 재질열화를 평가하기 위하여 고중압 터빈 로터의 고온증기가 통과하는 부위인 로터의 고압 터빈 입구 측과 중압 터빈 입구에 대해서 표면복제 관찰을 통해서 금속조직의 크리프 기공 성장 및 미세조직 변화를 분석하였다. 연구결과, 74,628시간 사용된 당진화력 4호기 고중압 터빈 로터의 미세조직 열화정도는 핀란드 Technical Research Centre 미세조직열화등급 기준으로 B등급이다. 그리고 Neubauer 크리프 기공 평가를 통해서 잔여수명은 201,523시간 이상으로 판단된다.

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고압 수증기하 산화에서 핵연료 피복관내 수소효과 연구 (The Effect of Hydrogen in the Nuclear Fuel Cladding on the Oxidation under High Temperature and High Pressure Steam)

  • 정윤목;정성기;박광헌;노선호
    • 한국표면공학회지
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    • 제47권1호
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    • pp.7-12
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    • 2014
  • The characteristics of oxidation for the Zry-4 was measured in the $800^{\circ}C$ and high steam pressure (50 bar, 75 bar, 100 bar) conditions, using an apparatus for high pressure steam oxidation. The effect of accelerated oxidation by high-pressure steam was increased more than 60% in hydrogen-charged cladding than normal cladding. This difference between hydrogen charged claddings and normal claddings tends to be larger as the higher pressure. The accelerated oxidation effect of hydrogen charging cladding is regarded as the hydrogen on the metal layer affects the formation of the protective oxide layer. The creation of the sound monoclinic phase in Zry-4 oxidation influences reinforcement of corrosion-resistance of the oxide layer. The oxidation is estimated to be accelerated due to the creation of equiaxial type oxide film with lower corrosion resistance than that of columnar type oxide film. When tetragonal oxide film transformed into the monoclinic oxide film, surface energy of the new monoclinic phase reduced by hydrogen in the metal layer.

스팀터빈의 공력성능 평가를 위한 공기 상사실험 (Air Similarity Test for the Evaluation of Aerodynamic Performance of Steam Turbine)

  • 임병준;이은석;양수석;이익형;김영상;권기범
    • 한국유체기계학회 논문집
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    • 제7권5호
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    • pp.29-35
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    • 2004
  • The turbine efficiency is an important factor in power plant, and accurate evaluation of steam turbine performance is the key issue in turbo machinery industry. The difficulty of evaluating the steam turbine performance due to its high steam temperature and pressure environment makes the most steam turbine tests to be replaced by air similarity test. This paper presents how to decide the similarity conditions of the steam turbine test and describes its limitations and assumptions. The test facility was developed and arranged to conduct an air similarity turbine performance test with various inlet pressure, temperature and mass flow rate. The eddy-current type dynamometer measures the turbine-generated shaft power and controls the rotating speed. Pressure ratio of turbine can be controled by back pressure control valve. To verify its test results, uncertainty analysis was performed and relative uncertainty of turbine efficiency was obtained.

Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility

  • Bae, Byoung-Uhn;Lee, Jae Bong;Park, Yu-Sun;Kim, Jongrok;Kang, Kyoung-Ho
    • Nuclear Engineering and Technology
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    • 제53권8호
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    • pp.2477-2487
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    • 2021
  • To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE. For a realistic simulation of a pressure and temperature (P/T) transient, the containment simulation vessel was designed to preserve a volumetric scale equivalently to the RCS volume scale of ATLAS. Three test cases for a steam line break (SLB) transient were conducted with variation of the initial condition of the passive heat sink or the steam flow direction. The test results indicated a stratified behavior of the steam-gas mixture in the containment following a high-temperature steam injection in prior to the spray injection. The test case with a reduced heat transfer on the passive heat sink showed a faster increase of the P/T inside the containment. The effect of the steam flow direction was also investigated with respect to a multi-dimensional distribution of the local heat transfer on the passive heat sink. The integral effect test data obtained in this study will contribute to validating the evaluation methodology for mass and energy (M/E) and P/T transient of the containment.

초음파 주파수분석법에 의한 발전소 고온배관재료의 크리프손상 평가 (Creep Damage Evaluation of High-Temperature Pipeline Material for Fossil Power Plant by Ultrasonic Frequency Analysis Spectrum Method)

  • 정민화;이상국
    • 한국해양공학회지
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    • 제13권2호통권32호
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    • pp.90-98
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    • 1999
  • Boiler high-temperature pipelines such as main steam pipe, header and steam drum in fossil power plants are degraded by creep damage due to severe operationg conditions like high temperature and high pressure for an extended period time. Such material degradation lead to various component faliures causing serious accidents at the plant. Conventional measurement techniques such as replica method, electric resistance method, and hardness test method have such disadvantages as complex preparation and measurement procedures, too many control parameters, and therefore, low practicality and they were applied only to component surfaces with good accessibility. In this study, both artificial creep degradation test using life prediction formula and frequency analysis by ultrasonic tests for their preparing creep degraded specimens have been carried out for the purpose of nondestructive evaluation for creep damage which can occur in high-temperature pipelline of fossil power plant. As a result of ultrasonic tests for crept specimens, we confirmed that the high frequency side spectra decrease and central frequency components shift to low frequency bans, and bandwiths decrease as increasing creep damage in backwall echoes.

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Calculation of the Reactance for a Magnetic Phase Created in a Steam Generator Tube Material

  • Ryu, Kwon-Sang;Jung, Jae-Kap;Son, Derac;Park, Duck-Gun
    • Journal of Magnetics
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    • 제15권2호
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    • pp.70-73
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    • 2010
  • A magnetic phase is partly produced in a steam generator tube due to stress and heat, because steam generator tubes are exposed to high temperature, high pressure and radioactivity conditions. This adversely affects the safety of steam generator tubes. However, it is difficult to detect it using conventional eddy current methods. Therefore, a new type of probe is needed to separate the signals from the defects and magnetic phases. In this study, a new U-type yoke, which contained two types of coils, a magnetizing coil and detecting coil, was designed. In addition, the signal induced by the magnetic phase and defect in an Inconel 600 plate were simulated.

증기터빈 과속도 보호장치의 비교분석 (An Analysis and Comparison of Steam Turbine Overspeed Protectors)

  • 최인규;정창기;김종안
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2004년도 하계학술대회 논문집 D
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    • pp.2260-2262
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    • 2004
  • After steam turbines in power plant drives generator and maintains it at rated speed using high temperature and high pressure steam energy, they regulate the output of generator when synchronized in parallel with the power system. 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 "how to limit the speed within its overspeed trip setpoint and escape from danger." For the purpose of it, there are various ways known. Some overspeed protection methods for steam turbines now being operating in korea are introduced in this paper.

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증기양생 조건에 따른 터널 PC 패널의 물리적 특성에 관한 연구 (The study on mechanical properties of PC panel with steam curing condition)

  • 마상준;장필성;신진용;남관우
    • 한국터널지하공간학회 논문집
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    • 제10권1호
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    • pp.17-24
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    • 2008
  • 국내에서 대부분 시공되어지고 있는 현장타설 콘크리트 라이닝은 여러 가지가 문제점을 나타내고 있다. 그 중에 특히 라이닝의 균열 발생은 사회적 및 경제적인 문제로까지 제기되고 있으며 라이닝의 미관뿐만 아니라 안정성에도 영향을 미치게 되므로 막대한 보수보강 공사비의 지출을 유발해 국가 예산을 소모시키고 있다. 국내 콘크리트 2차 제품 생산업체의 생산기술은 아직 선진국 수준에 미치지 못하며, 고품질 제품 생산에 있어 가장 중요한 증기양생 방법 또한 규정되어 있지 않은 실정이다. 본 연구에서는 터널용 PC 패널의 증기양생조건 중 전양생시간, 온도상승구배를 달리하여 물리적 특성을 검토하였다. 시험결과, 고강도 PC패널의 전양생시간은 최소 1시간 이상이 바람직하였으며 온도상승구배는 최대 $20^{\circ}C$가 물리 역학적으로 가장 우수한 성능을 나타내었다.

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Spontaneous Steam Explosions Observed In The Fuel Coolant Interaction Experiments Using Reactor Materials

  • Jinho Song;Park, Ikkyu;Yongseung Sin;Kim, Jonghwan;Seongwan Hong;Byungtae Min;Kim, Heedong
    • Nuclear Engineering and Technology
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    • 제34권4호
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    • pp.344-357
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    • 2002
  • The present paper reports spontaneous steam explosions observed in fuel coolant interaction experiments using prototypic reactor materials. Pure ZrO$_2$ and a mixture of UO$_2$ and ZrO$_2$ are used. A high temperature molten material in the form of a jet is poured into a subcooled water pool located in a pressure vessel. An induction skull melting technique is used for the melting of the reactor material. In both tests using pure ZrO$_2$ and a mixture of UO$_2$ and ZrO$_2$, either a quenching or a spontaneous steam explosion was observed. The morphology of debris and pressure profile clearly indicate the differences between the qunching cases and explosion cases. The dynamic pressure. dynamic impulse, water temperature, melt temperature, and static pressure Inside the containment chamber were measured . As the spontaneous steam explosion for the reactor material is firstly observed in the present experiments, the results of present experiments could be a siginificant step forward the understanding the explosion of the reactor material.