• Title/Summary/Keyword: Transient thermal load

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Power Quality Analysis of Jeju Power System during HVDC Overhaul using PSCAD/EMTDC (PSCAD/EMTDC에 의한 직류연계선 오버홀시 제주계통의 전력품질 분석)

  • Kang, Bo-Seung;Kim, Jae-Hong;Kim, Eel-Hwan;Kim, Se-Ho;Oh, Seong-Bo;Song, Ki-Heouk
    • Proceedings of the KIPE Conference
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    • 2008.06a
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    • pp.82-84
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    • 2008
  • This paper presents the modeling and power quality analysis of Jeju island power system connected with wind farm, and thermal power plant. It is for indicating the influence of wind farm operation in steady and transient state in Jeju island power system during the HVDC system overhaul period. For the computer simulation, three kinds of main item are modeled, which are 67[MW] wind farm, thermal power plant and Jeju power load. To analyze the influence of the wind power generation to the Jeju power system, two kinds of simulations are carried out by using the PSCAD/EMTDC program. One is the steady state operation under the variable speed wind, and the other is the transient state operation when all of wind farms in Jeju island are disconnected from the Jeju power grid instantaneously on the rated power output. With the comparison of these results, it is useful for analyzing the power quality of Jeju power system versus wind power generation.

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Numerical analysis for behavior of outer concrete tank in emergency LNG spillage

  • Lee, Jeong Su;Park, Chan Kyu;Lee, Yun;Kim, Ji-Hoon;Kwon, Seung Hee
    • Computers and Concrete
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    • v.14 no.4
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    • pp.369-385
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    • 2014
  • In the existing method for analyzing the liquid tightness of the outer concrete tank in an emergency LNG spillage, the temperature variation over time inside the tank, and the concrete properties dependent on temperature and internal moisture content, have not been taken into account. In this study, the analyses for a typical LNG concrete tank subjected to thermal load due to spillage were performed with three different cases: the existing method was adopted in the first case, the transient temperature variation was considered in the second, and the temperature-moisture content dependent concrete properties were taken into account as well as the transient states of temperature in the third. The analysis results for deformation, compressive zone size, cracking, and stress of reinforcements were compared, and a discussion on the difference between the results obtained from the different analysis cases was made.

Transient thermal stress of CFRP propellant tank depending on charging speed of cryogenic fluid

  • Jeon, Seungmin;Kim, Dongmin;Kim, Jungmyung;Choi, Sooyoung;Kim, Seokho
    • Progress in Superconductivity and Cryogenics
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    • v.22 no.4
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    • pp.51-56
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    • 2020
  • In order to increase thrust of the space launch vehicle, liquid oxygen as an oxidizer and kerosene or liquid hydrogen as a fuel are generally used. The oxidizer tank and fuel tanks are manufactured by composite materials such as CFRP (Carbon Fiber Reinforced Plastic) to increase pay load. The thermal stress of the cryogenic propellant tank should be considered because it has large temperature gradient. In this study, to confirm the design integrity of the oxidizer tank of liquid oxygen, a numerical analysis was conducted on the thermal stress and temperature distribution of the tank for various charging speed of the cryogenic fluid from 100 ~ 900 LPM taking into account the evaporation rate of the liquid nitrogen by convective heat transfer outside the tank and boiling heat transfer inside the tank. The thermal stress was also calculated coupled with the temperature distribution of the CFRP tank. Based on the analysis results, the charging speed of the LN2 can majorly affects the charging time and the resultant thermal stress.

Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers

  • Xicheng Wang;Dmitry Grishchenko;Pavel Kudinov
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.1052-1065
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    • 2024
  • Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both normal and accident conditions. Direct Contact Condensation (DCC) creates sources of momentum and heat. The competition between these two sources determines the development of thermal stratification or mixing of the pool. Thermal stratification is of safety concern as it reduces the cooling capability compared to a completely mixed pool condition. In this work we develop a scaling approach to prediction of the thermal stratification in a water pool induced by steam injection through spargers. Experimental data obtained from large-scale pool tests conducted in the PPOOLEX and PANDA facilities, as well as simulation results obtained using validated codes are used to develop the scaling. Two injection orientations, namely radial injection through multi-hole Sparger Head (SH) and vertical injection through Load Reduction Ring (LRR), are considered. We show that the erosion rate of the cold layer can be estimated using the Richardson number. In this work, scaling laws are proposed to estimate both the (i) transient erosion velocity and (ii) the stable position of the thermocline. These scaling laws are then implemented into a 1D model to simulate the thermal behavior of the pool during steam injection through the sparger.

Nonlinear Analysis of Nuclear Reinforced Concrete Containment Structures under Accidental Thermal Load and Pressure (온도 및 내압을 받는 원자로 철근콘크리트 격납구조물의 비선형해석)

  • Oh, Byung Hwan;Lee, Myung Gue
    • KSCE Journal of Civil and Environmental Engineering Research
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    • v.14 no.3
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    • pp.403-414
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    • 1994
  • Nonlinear analysis of RC containment structure under thermal load and pressure is presented to trace the behaviour after an assumed LOCA. The temperature distribution varying with time through the wall thickness is determined by transient finite element analysis with the two time level scheme in time domain. The layered shell finite elements are used to represent the containment structures in nuclear power plants. Both geometric and material nonlinearities are taken into account in the finite element formulation. The constitutive relation of concrete is modeled according to Drucker-Prager yield criteria in compression. Tension stiffening model is used to represent the tensile behaviour of concrete including bond effect. The reinforcing bars are modeled by smeared layer at the location of reinforcements accounting elasto-plastic axial behaviors. The steel liner model under Von Mises yield criteria is adopted to represent elastic-perfect plastic behaviour. Geometric nonlinearity is formulated to consider the large displacement effect. Thermal stress components are determined by the initial strain concept during each time step. The temperature differential between any two consecutive time steps is considered as a load incremental. The numerical results from this study reveal that nonlinear temperature gradient based on transient thermal analysis will produces excessive large displacement. Nonlinear behavior of containment structures up to ultimate stage can be traced reallistically. The present study allows more realistic analysis of concrete containment structures in nuclear power plants.

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Stress and Fatigue Evaluation of Distributor for Heat Recovery Steam Generator in Combined Cycle Power Plant (복합발전플랜트 배열회수보일러 분배기의 응력 및 피로 평가)

  • Lee, Boo-Youn
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.19 no.8
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    • pp.44-54
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    • 2018
  • Stress and fatigue of the distributor, an equipment of the high-pressure evaporator for the HRSG, were evaluated according to ASME Boiler & Pressure Vessel Code Section VIII Division 2. First, from the results of the piping system analysis model, reaction forces of the tubes connected to the distributor were derived and used as the nozzle load applied to the detailed analysis model of the distributor afterward. Next, the detailed model to analyze the distributor was constructed, the distributor being statically analyzed for the design condition with the steam pressure and the nozzle load. As a result, the maximum stress occurred at the bore of the horizontal nozzle, and the primary membrane stress at the shell and nozzle was found to be less than the allowable. Next, for the transient operating conditions given for the distributor, thermal analysis was performed and the structural analysis was carried out with the steam pressure, nozzle load, and thermal load. Under the transient conditions, the maximum stress occurred at the vertical downcomer nozzle, and of which fatigue life was evaluated. As a result, the cumulative usage factor was less than the allowable and hence the distributor was found to be safe from fatigue failure.

CORIUM BEHAVIOR IN THE LOWER PLENUM OF THE REACTOR VESSEL UNDER IVR-ERVC CONDITION: TECHNICAL ISSUES

  • Park, Rae-Joon;Kang, Kyoung-Ho;Hong, Seong-Wan;Kim, Sang-Baik;Song, Jin-Ho
    • Nuclear Engineering and Technology
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    • v.44 no.3
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    • pp.237-248
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    • 2012
  • Corium behavior in the lower plenum of the reactor vessel during a severe accident is very important, as this affects a failure mechanism of the lower head vessel and a thermal load to the outer reactor vessel under the IVR-ERVC (In-Vessel corium Retention through External Reactor Vessel Cooling) condition. This paper discusses the state of the art and technical issues on corium behavior in the lower plenum, such as initial corium pool formation characteristics and its transient behavior, natural convection heat transfer in various geometries, natural convection heat transfer with a phase change of melting and solidification, and corium interaction with a lower head vessel including penetrations of the ICI (In-Core Instrumentation) nozzle are discussed. It is recommended that more detailed analysis and experiments are necessary to solve the uncertainties of corium behavior in the lower plenum of the reactor vessel.

Evaluation on Residual Compressive Strength and Strain Properties of Ultra High Strength Concrete with Design Load and Elevated Temperature (설계하중 및 고온을 받은 초고강도 콘크리트의 잔존압축강도 및 변형 특성 평가)

  • Yoon, Min-Ho;Kim, Gyu-Yong;Nam, Jeong-Soo;Yun, Jong-Il;Bae, Chang-O;Choe, Gyeong-Cheol
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2012.11a
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    • pp.263-264
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    • 2012
  • In this study, the ultra high strength concrete which have 100, 150, 200MPa took the heat from 20℃ to 70 0℃ and the 0, 20% stress in normal condition's to evaluate stress-strain, residual compressive strength and thermal expansion deformation were evaluated. The heating speed of specimen was 0.77℃/min 20~50℃, 50℃ before the target temperature, and the other interval's heating speed was 1℃/min. As a result, the stress-strain curve of non-load specimen showed the liner behavior at high temperature when the specimen's strength increased more. If ultra high strength concrete got loads, its compressive strength tended to decrease different from the normal strength concrete. The thermal expansion deformation was expanded from a vitrification of quartz over 500℃. however, over the 600℃, it was shrinked because of the dehydration of the combined water.

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Thermopiezoelastic Nonlinear Dynamic Characteristics of Piezolaminated Plates (압전적층판의 열-압전-탄성 동적 비선형 작동특성)

  • Oh, Il-Kwon
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2005.05a
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    • pp.662-667
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    • 2005
  • Nonlinear dynamics of active piezolaminated plates are investigated with respect to the thermopiezoelastic behaviors. For largely deformed structures with small strain, the incremental total Lagrangian formulation is presented based on the virtual work principles. A multi field layer wise finite shell element is proposed for assuring high accuracy and non-linearity of displacement, electric and thermal fields. For dynamic consideration of thermopiezoelastic snap through phenomena, the implicit Newmark's scheme with the Newton-Raphson iteration is implemented for the transient response of various piezolaminated models with symmetric or eccentric active layers. The bifurcate thermal buckling of symmetric structural models is first investigated and the characteristics of piezoelectric active responses are studied for finding snap through piezoelectric potentials and the load path tracking map. The thermoelastic stable and unstable postbuckling, thermopiezoelastic snap through phenomena with several attractors are proved using the nonlinear time responses for various initial conditions and damping loss factors. Present results show that thermopiezoelastic snap through phenomena can result in the difficulty of buckling and postbuckling control of intelligent structures.

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An Experimental Study on the Heat Transfer Characteristics of High-Temperature Cylindrical Heat Pipes (고온 원관형 히트파이프의 열전달 특성에 관한 실험 연구)

  • 박수용;부준홍
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.16 no.1
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    • pp.70-76
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    • 2004
  • High-temperature cylindrical sodium/stainless-steel heat pipes were manufactured and tested for transient as well as steady states. Total length of the heat pipe was 1 m and the diameter was 25.4 mm. Screen meshes of 3 different sizes were used to estimate the effect of mesh size on the thermal performance of the heat pipe. The minimum thermal resistance achieved was as low as 0.02$^{\circ}C$/W for the maximum thormal load of 2 ㎾. The average heat transfer coefficient in the evaporator was about 2,000 ㎾/$m^2$K and those in the condenser region were up to 5 times higher.