• 제목/요약/키워드: Water-Steam Dynamic Flow

검색결과 28건 처리시간 0.022초

석탄 가스화 반응의 동적 거동 전산 모사 (Dynamic Modeling of Gasification Reactions in Entrained Coal Gasifier)

  • 지준화;오민;김시문;김미영;이중원;김의식
    • 한국수소및신에너지학회논문집
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    • 제22권3호
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    • pp.386-401
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    • 2011
  • Mathematical models for various steps in coal gasification reactions were developed and applied to investigate the effects of operation parameters on dynamic behavior of gasification process. Chemical reactions considered in these models were pyrolysis, volatile combustion, water shift reaction, steam-methane reformation, and char gasification. Kinetics of heterogeneous reactions between char and gaseous agents was based on Random pore model. Momentum balance and Stokes' law were used to estimate the residence time of solid particles (char) in an up-flow reactor. The effects of operation parameters on syngas composition, reaction temperature, carbon conversion were verified. Parameters considered here for this purpose were $O_2$-to-coal mass ratio, pressure of reactor, composition of coal, diameter of char particle. On the basis of these parametric studies some quantitative parameter-response relationships were established from both dynamic and steady-state point of view. Without depending on steady state approximation, the present model can describe both transient and long-time limit behavior of the gasification system and accordingly serve as a proto-type dynamic simulator of coal gasification process. Incorporation of heat transfer through heterogenous boundaries, slag formation and steam generation is under progress and additional refinement of mathematical models to reflect the actual design of commercial gasifiers will be made in the near futureK.

A study on the dynamic characteristics of the secondary loop in nuclear power plant

  • Zhang, J.;Yin, S.S.;Chen, L.;Ma, Y.C.;Wang, M.J.;Fu, H.;Wu, Y.W.;Tian, W.X.;Qiu, S.Z.;Su, G.H.
    • Nuclear Engineering and Technology
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    • 제53권5호
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    • pp.1436-1445
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    • 2021
  • To obtain the dynamic characteristics of reactor secondary circuit under transient conditions, the system analysis program was developed in this study, where dynamic models of secondary circuit were established. The heat transfer process and the mechanical energy transfer process are modularized. Models of main equipment were built, including main turbine, condenser, steam pipe and feedwater system. The established models were verified by design value. The simulation of the secondary circuit system was conducted based on the verified models. The system response and characteristics were investigated based on the parameter transients under emergency shutdown and overload. Various operating conditions like turbine emergency shutdown and overspeed, condenser high water level, ejector failures were studied. The secondary circuit system ensures sufficient design margin to withstand the pressure and flow fluctuations. The adjustment of exhaust valve group could maintain the system pressure within a safe range, at the expense of steam quality. The condenser could rapidly take out most heat to avoid overpressure.

수치 모사를 통한 사출관 내부의 열유동 해석 (Thermo-fluid Dynamic Analysis through a Numerical Simulation of Canister)

  • 김현묵;배성훈;박철현;전혁수;김정수
    • 한국추진공학회지
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    • 제21권1호
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    • pp.72-83
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    • 2017
  • 본 연구에서는 유도탄 사출관 내부의 수치모사를 통해 이상 유동에 대한 열 유체역학적 분석을 수행하였다. 고정된 해석영역에서 계산이 진행되었고 증발이 완료된 물을 냉각제로 사용하였다. 고온의 공기와 냉각제간의 상호작용 및 유동장을 해석하기 위해, Realizable $k-{\varepsilon}$ 난류 모델과 VOF (Volume Of Fluid) 모델을 선정하고 냉각제 유량에 따른 수치 해석을 진행하였다. 해석결과, 사출관 상부 압력은 냉각제 유량에 따라 비선형적으로 증가하였다. 그리고 내부에서의 유동 진행 과정과 온도분포, 냉각제분포가 밀접한 연관이 있음을 확인하였다. 사출관 하부의 초기 온도는 냉각제량의 증가에 비례하여 감소하지만, 특정시간 이후 경향이 역전되면서 오히려 온도의 상승을 유발하였다. 또한, 혼합가스의 순환유동에 의해 초기의 온도변화가 요동하는 경향도 확인되었다.

System dynamics simulation of the thermal dynamic processes in nuclear power plants

  • El-Sefy, Mohamed;Ezzeldin, Mohamed;El-Dakhakhni, Wael;Wiebe, Lydell;Nagasaki, Shinya
    • Nuclear Engineering and Technology
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    • 제51권6호
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    • pp.1540-1553
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    • 2019
  • A nuclear power plant (NPP) is a highly complex system-of-systems as manifested through its internal systems interdependence. The negative impact of such interdependence was demonstrated through the 2011 Fukushima Daiichi nuclear disaster. As such, there is a critical need for new strategies to overcome the limitations of current risk assessment techniques (e.g. the use of static event and fault tree schemes), particularly through simulation of the nonlinear dynamic feedback mechanisms between the different NPP systems/components. As the first and key step towards developing an integrated NPP dynamic probabilistic risk assessment platform that can account for such feedback mechanisms, the current study adopts a system dynamics simulation approach to model the thermal dynamic processes in: the reactor core; the secondary coolant system; and the pressurized water reactor. The reactor core and secondary coolant system parameters used to develop system dynamics models are based on those of the Palo Verde Nuclear Generating Station. These three system dynamics models are subsequently validated, using results from published work, under different system perturbations including the change in reactivity, the steam valve coefficient, the primary coolant flow, and others. Moving forward, the developed system dynamics models can be integrated with other interacting processes within a NPP to form the basis of a dynamic system-level (systemic) risk assessment tool.

저출력 및 과도상태시 원전 증기발생기 수위제어에 관한 연구 (A Study on Water Level Control of PWR Steam Generator at Low Power Operation and Transient States)

  • 나난주;권기춘;변증남
    • 한국지능시스템학회논문지
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    • 제3권2호
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    • pp.18-35
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    • 1993
  • 가압경수로형 원자력발전소 수위제어시스템과 특히 저출력시 수위제어상의 문제점들이 분석 및 고찰되었으며 저출력으로 운전시의 여러 과도특성에서도 안정된 제어를 하고 급수펌프고장과 같은 큰 수위변동 발생시에는 신속한 수위응답을 얻기 위한 방법이 주로 연구되었다. 제어기의 기본 알고리즘으로 퍼지제어기법을 적용하였으며 여기에 필요한 제어규칙 및 알고리즘은 운전원의 지식과 한국원자력연구소에 설치된 교육훈련용 모의제어반에서의 수동운전경험을 바탕으로 설정되었다. 실제 시스템 구현관점에서 제어변수 및 적용규칙은 보다 간편한 튜닝과 입출력변수간의 영향을 고려하여 세워졌다. 저유량일 때 측정이 불량한 유량신호에 대해, 중기발생기를 압력제어모드로 운전할 때에는 유량차의 퍼지변수로서 우회급수밸브의 개도를 이용한 대체정보를 채용하였으며 수위오차의 크기에 따라 유량차의 소속함수를 달리하는 동적인 튜닝방법을 사용하였다. 또한 우회급수와 주급수밸브간 간단한 전환알고리즘의 적용으로 밸브절환시의 수위요동을 억제하고자 하였다. 시뮬레이션 결과 저출력구간에서 원자로출력변동에 대해 기존에 설치된 방법보다 안정된 제어를 하고 동적 튜닝의 적용으로 미세제어동작과 수위오차가 큰 영역의 제어에 대해 신속한 응답과 함께 제어성능이 개선되었음을 보였다.

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2상 횡유동에서 열교환기 관군 배치에 다른 진동특성 고찰 (The effects of tube bundle geometry on vibration in two-phase cross-flow)

  • 김범식
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2001년도 춘계학술대회논문집
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    • pp.681-687
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    • 2001
  • Two-phase cross-flow exists in many shell-tube heat exchangers such as steam generators, condensers and reboilers. An understanding of flow-induced vibration excitation mechanism is necessary to avoid problems due to excessive tube vibration. This paper presents the results of a series of experiments done on tube bundles of different geometries subjected to two-phase cross-flow simulated by air-water mixtures. Normal(30$^{\circ}$) and rotated (60$^{\circ}$)triangular, and normal(90$^{\circ}$) and rotated (45$^{\circ}$) square tube bundle configurations of pitch-to-diameter ratio of 1.2 to 1.5 were tested over a range of mass fluxes from 0 to 1,000kg/$m^2$ㆍ s and void fraction from 0 to 100%. The effects of tube bundle geometry on vibration excitation mechanism such as fluidelastic instability and random turbulence, and on dynamic parameters such as damping and hydrodynamic mass are discussed. A lower pitch-to-diameter results in a higher hydrodynamic mass. The effect of tube bundle configurations on damping and random turbulence excitation is minor. The effect of pitch-to-diameter on the fluidelastic instability, however, is significant.

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비례유량제어밸브 위치제어기 자동조정 (Auto Tuning of Position Controller for Proportional Flow Control Solenoid Valve)

  • 정규홍
    • 대한기계학회논문집A
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    • 제36권7호
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    • pp.797-803
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    • 2012
  • 비례솔레노이드밸브는 코일전류에 비례하는 전자기력을 이용하여 밸브 변위를 연속적으로 가변시키는 밸브이다. 대용량 비례유량제어밸브는 발전소나 화학 플랜트에서 물, 스팀, 가스 등과 같은 공정유체의 대용량 유량제어에 사용되며 공압이나 모터를 이용하는 밸브에 비하여 우수한 응답성능과 소형화의 장점을 가진다. 본 연구에서는 비례제어밸브를 대상으로 밸브의 동적 특성을 식별한 후 목표 성능이 만족되도록 위치제어기의 비례적분이득을 자동으로 조정하는 기능을 설계하였다. 동특성 식별은 릴레이 피드백을 통하여 한계 안정 상태에서의 임계이득과 임계주기로 파악하였으며, 비례적분이득 결정에는 Ziegler-Nichols 방법을 적용하였다. 구현된 기능은 시험을 통하여 성능을 검증하였으며 밸브 작동점과 릴레이 제어기 변수가 자동조정에 미치는 영향을 분석하였다.

대규모 태양열발전 기본설계 및 동특성 계산 (Basic Design and Dynamic Simulation of Large Scale Solar Thermal Power Plant)

  • 김종규;강용혁;김진수;윤환기;유창균;이상남
    • 한국태양에너지학회 논문집
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    • 제27권1호
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    • pp.55-61
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    • 2007
  • This paper describes the procedure and calculation results of basic design and transient variation of performance of 1 MWe large scale solar thermal power plant (STPP) by using the commercial software of THERMOFLEX and TRNSYS, respectively. In order to simulate the transient variation of STPP, the results of basic design are necessary. The design standard of the STPP is 1 MWe generation with solar only at high DNI condition and then 0.6 MWe output power for 1 hour using stored energy when the DNI becomes lower unable to operate normally. The results of basic design show the important design data of flow rates, water/steam conditions at each equipments and the estimated efficiency of STPP. In addition, dynamic simulation results of STPP are predicted and plotted for one year and three different days weather data of Daejeon.