• 제목/요약/키워드: Core inlet

검색결과 117건 처리시간 0.023초

밀리미터 스케일 촉매 연소기에서의 수소-공기 예혼합 가스의 촉매 연소 특성 (Catalytic Combustion Characteristics of Hydrogen-Air Premixture in a Millimeter Scale Monolith Coated with Platinum)

  • 최원영;권세진
    • 한국연소학회지
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    • 제10권1호
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    • pp.20-26
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    • 2005
  • In the present study, catalytic combustion of hydrogen-air premixture in a millimeter scale monolith coated with Pt catalyst was investigated. As the combustor size decreases, the heat loss increases in proportion with the inverse of the scale of combustion chamber and combustion efficiency decreases in a conventional type of combustor. Combustion reaction assisted by catalyst can reduce the heat loss by decreasing the reaction temperature at which catalytic conversion takes place. Another advantage of catalytic combustion is that ignition is not required. Platinum was coated by incipient wetness method on a millimeter scale monolith with cell size of $1{\times}1mm$. Using this monolith as the core of the reaction chamber, temperatures were recorded at various locations along the flow direction. Burnt gas was passed to a gas chromatography system to measure the hydrogen content after the reaction. The measurements were made at various volume flow rate of the fuel-air premixture. The gas chromatography results showed the reaction was complete at all the test conditions and the reacting species penetrated the laminar boundary layer at the honeycomb and made contact with the catalyst coated surface. At all the measuring locations, the record showed monotonous increase of temperature during the measurement duration. And the temperature profile showed that the peak temperature is reached at the point nearest to the gas inlet and decreasing temperature along the flow direction.

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마이크로 가스터빈 엔진 개발 (Development of the Micro Gas Turbine Engine)

  • 김승우;권기훈;장일형
    • 유체기계공업학회:학술대회논문집
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    • 유체기계공업학회 2001년도 유체기계 연구개발 발표회 논문집
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    • pp.361-366
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    • 2001
  • A mim turbo-shaft engine of 50HP for UAV, which can be easily modified to turbo-prop and turbo-jet engine by sharing the core engine and has many applications to civilian demands and munitions, will be developed This kind of micro gas turbine engine has been developed mostly by the corporations which have special technology but are small in its scale. Especially, the gas turbine engine can be easily applied to other fields and developed by domestic technology, so that the sharing of technology is planed to realize through the cooperations with academies and research institutes. In this paper, the gas turbine engine, which has the compressor ratio of 3.8, the turbine inlet temperature of l180K and the engine speed higher than 100,000 rpm, is composed of centrifugal compressor, combustor, gas generator turbine, free power turbine and gear box. The competitiveness of the gas turbine engine can be obtained from minimizing its cost by the utilization of domestic infrastructure for the performance test and the decisive outsourcing.

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수치모의를 통한 유사제트-파랑의 상호작용 해석 (Analysis of Interaction of Jet-like Current and Wave using Numerical Simulation)

  • 최준우;배재석;노민;윤성범
    • 한국전산유체공학회:학술대회논문집
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    • 한국전산유체공학회 2008년도 춘계학술대회논문집
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    • pp.675-678
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    • 2008
  • The effect of wave and current interactions on jet-like current flowing against waves was investigated based on numerical simulations. The numerical simulations are conducted by a combined model system of REF/DIF(a wave model) plus SHORECIRC(a current model) and a Boussinesq equation model, FUNWAVE. In the simulations, regular and irregular waves refracted due to the jet-like opposing current were focused along the core region of current, and the jet-like current was earlier spreaded when the waves had larger wave heights. The numerical results show that the rapid change of wave height distribution in transverse direction near current inlet plays a significant role to spread the jet-like current. In other words, the gradients of radiation stress forcing in transverse direction have a more significant effect on the jet-like current than its relatively small gradients forcing in flowing direction, which tend to accelerate the current, do. In conclusion, it is indispensible to take into account the interaction effect of wave transformation and current characteristics when waves meet the opposing jet-like current such as river mouth.

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전산 구조해석을 이용한 산화제 개폐밸브 성능향상에 관한 연구 (Study on the performance improvement of a Main Oxidizer shut-off Valve Using Computer Aided Structural Analysis)

  • 김도형;배영우;홍문근;유재한;김은수;장기원
    • 한국추진공학회:학술대회논문집
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    • 한국추진공학회 2010년도 제35회 추계학술대회논문집
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    • pp.111-114
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    • 2010
  • 발사체 추진시스템에서 CC(Combustion Chamber) 산화제 개폐밸브는 액체산소를 연소기로 공급 및 차단함으로써 연소를 개시 및 중단시킬 뿐만 아니라, 정상운영 상태에서는 연소기 내 안정된 연소가 가능하도록 일정한 유량의 액체산소를 공급한다. 개발이 완료된 산화제 개폐밸브 EM(Engineering Model)의 주요 구성부의 성능향상을 위하여 전산구조해석을 이용한 중간플랜지, 밸브 입구의 립 부분의 설계 변경을 수행하였으며, 성능 시험을 통하여 설계변경에 의한 성능 향상을 최종확인 하였다.

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NUMERICAL ANALYSIS OF THERMAL STRATIFICATION IN THE UPPER PLENUM OF THE MONJU FAST REACTOR

  • Choi, Seok-Ki;Lee, Tae-Ho;Kim, Yeong-Il;Hahn, Dohee
    • Nuclear Engineering and Technology
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    • 제45권2호
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    • pp.191-202
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    • 2013
  • A numerical analysis of thermal stratification in the upper plenum of the MONJU fast breeder reactor was performed. Calculations were performed for a 1/6 simplified model of the MONJU reactor using the commercial code, CFX-13. To better resolve the geometrically complex upper core structure of the MONJU reactor, the porous media approach was adopted for the simulation. First, a steady state solution was obtained and the transient solutions were then obtained for the turbine trip test conducted in December 1995. The time dependent inlet conditions for the mass flow rate and temperature were provided by JAEA. Good agreement with the experimental data was observed for steady state solution. The numerical solution of the transient analysis shows the formation of thermal stratification within the upper plenum of the reactor vessel during the turbine trip test. The temporal variations of temperature were predicted accurately by the present method in the initial rapid coastdown period (~300 seconds). However, transient numerical solutions show a faster thermal mixing than that observed in the experiment after the initial coastdown period. A nearly homogenization of the temperature field in the upper plenum is predicted after about 900 seconds, which is a much shorter-term thermal stratification than the experimental data indicates. This discrepancy may be due to the shortcoming of the turbulence models available in the CFX-13 code for a natural convection flow with thermal stratification.

Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor

  • Chang, Seok-Kyu;Euh, Dong-Jin;Choi, Hae Seob;Kim, Hyungmo;Choi, Sun Rock;Lee, Hyeong-Yeon
    • Nuclear Engineering and Technology
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    • 제48권2호
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    • pp.376-385
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    • 2016
  • A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design. The iso-kinetic sampling method has been adopted to measure the flow rate at subchannels, and newly designed sampling probes which preserve the flow area of subchannels have been devised. Experimental tests have been performed at 20-115% of the nominal flow rate and $60^{\circ}C$ (equivalent to Re ~ 37,100) at the inlet of the test rig. The pressure loss data in three measured subchannels were almost identical regardless of the subchannel locations. The flow rate at each type of subchannel was identified and the flow split factors were evaluated from the measured data. The predicted correlations and the computational fluid dynamics results agreed reasonably with the experimental data.

Modelling of multidimensional effects in thermal-hydraulic system codes under asymmetric flow conditions - Simulation of ROCOM tests 1.1 and 2.1 with ATHLET 3D-Module

  • Pescador, E. Diaz;Schafer, F.;Kliem, S.
    • Nuclear Engineering and Technology
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    • 제53권10호
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    • pp.3182-3195
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    • 2021
  • The implementation and validation of multi-dimensional (multi-D) features in thermal-hydraulic system codes aims to extend the application of these codes towards multi-scale simulations. The main goal is the simulation of large-scale three-dimensional effects inside large volumes such as piping or vessel. This novel approach becomes especially relevant during the simulation of accidents with strongly asymmetric flow conditions entailing density gradients. Under such conditions, coolant mixing is a key phenomenon on the eventual variation of the coolant temperature and/or boron concentration at the core inlet and on the extent of a local re-criticality based on the reactivity feedback effects. This approach presents several advantages compared to CFD calculations, mainly concerning the model size and computational efforts. However, the range of applicability and accuracy of the newly implemented physical models at this point is still limited and needs to be further extended. This paper aims at contributing to the validation of the multi-D features of the system code ATHLET based on the simulation of the Tests 1.1 and 2.1, conducted at the test facility ROCOM. Overall, the multi-D features of ATHLET predict reasonably well the evolution from both experiments, despite an observed overprediction of coolant mixing at the vessel during both experiments.

Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests

  • Zonglan Wei;Bojan Niceno ;Riccardo Puragliesi;Ezequiel Fogliatto
    • Nuclear Engineering and Technology
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    • 제54권11호
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    • pp.4359-4372
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    • 2022
  • Turbulent mixing in buoyant flows is an essential mechanism involved in many scenarios related to nuclear safety in nuclear power plants. Comprehensive understanding and accurate predictions of turbulent buoyant flows in the reactor are of crucial importance, due to the function of mitigating the potential detrimental consequences during postulated accidents. The present study uses URANS methodology to investigate the buoyancy-influenced flows in the reactor pressure vessel under the main steam line break accident scenarios. With a particular focus on the influence of turbulent heat flux closure models, various combinations of two turbulence models and three turbulent heat flux models are utilized for the numerical simulations of three ROCOM tests which have different characteristic features in terms of the flow rate and fluid density difference between loops. The simulation results are compared with experimental measurements of the so-called mixing scalar in the downcomer and at the core inlet. The study shows that the anisotropic turbulent heat flux models are able to improve the accuracy of the predictions under conditions of strong buoyancy whilst in the weak buoyancy case, a major role is played by the selected turbulence models with essentially a negligible influence of the turbulent heat flux closure models.

Thermo-hydrodynamic investigation into the effects of minichannel configuration on the thermal performance of subcooled flow boiling

  • Amal Igaadi;Rachid El Amraoui;Hicham El Mghari
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.265-274
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    • 2024
  • The current research focuses on the development of a numerical approach to forecast strongly subcooled flow boiling of FC-72 as the refrigerant in various vertical minichannel shapes for high-heat-flux cooling applications. The simulations are carried out using the Volume of Fluid method with the Lee phase change model, which revealed some inherent flaws in multiphase flows that are primarily due to an insufficient interpretation of shearlift force on bubbles and conjugate heat transfer against the walls. A user-defined function (UDF) is used to provide specific information about this noticeable effect. The influence of shape and the inlet mass fluxes on the flow patterns, heat transfer, and pressure drop characteristics are discussed. The computational results are validated with experimental measurements, where excellent agreements are found that prove the efficiency of the present numerical model. The findings demonstrate that the heat transfer coefficient decreases as the mass flux increases and that the constriction design improves the thermal performance by 24.68% and 10.45% compared to the straight and expansion shapes, respectively. The periodic constriction sections ensure good mixing between the core and near-wall layers. In addition, a slight pressure drop penalty versus the thermal transfer benefits for the two configurations proposed is reported.

관수온도 상승률 증가에 의한 발전용 보일러의 온간기동시간 단축에 관한 연구 (Warm Start Up Time Reduction Through the Increase of Boiler Water Circulating Pump Inlet Water Temperature Rate of the Thermal Power Plant)

  • 강희성;문승재
    • 플랜트 저널
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    • 제10권1호
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    • pp.47-53
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    • 2014
  • 1887년 경복궁 건천궁에서 최초로 전기점등 행사를 시행한 이후 2012년 11월 기준의 대한민국 발전설비 용량은 81,737 MW, 그리고 2012년도 최대전력 수요는 71,230 MW로 이전기록을 경신한 바 있다. 이렇게 급속하게 증가하는 전력수요를 충족하기 위하여 정부에서는 대용량 유연탄 화력과 원자력발전소를 건설하여 운영 중에 있으나 전력수요는 주중에 집중되고 주말에는 급감하여 주말의 예비률이 40% 이상을 상회하고 있어 양수발전기를 이용하여 주말수요를 창출하는 한편 감소된 주말의 전력수요에 맞추어 서울화력발전소을 포함한 고원가 발전소에 대한 주말정지를 시행하고 있다. 서울화력발전소는 전력수요지의 중심지인 수도 서울에 위치하였음에도 발전원가가 높아 2008년도 이후 매년 30회 이상의 주말정지를 시행함으로 기동정지 과정에서 많은 비용을 지출하고 있어 본 연구에서는 1969년 준공하여 열병합설비로 개조한 서울화력발전소 제5호기를 대상으로 온간기동 과정에서 보일러 강제순환펌프 입구 관수온도 상승률을 증가시켜 온도상승 공정에 소요되는 시간을 약 35% 단축하고 기동시간 종합관리 프로그램을 구성하여 운영함으로써 전체적으로 온간기동 시간을 23% 단축할 수 있음을 확인하였다.

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