• 제목/요약/키워드: potential-flow models

검색결과 115건 처리시간 0.038초

중회귀 모형을 이용한 울산지역 오존 포텐셜 모형의 설계 및 평가 (Design and Assessment of an Ozone Potential Forecasting Model using Multi-regression Equations in Ulsan Metropolitan Area)

  • 김유근;이소영;임윤규;송상근
    • 한국대기환경학회지
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    • 제23권1호
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    • pp.14-28
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    • 2007
  • This study presented the selection of ozone ($O_3$) potential factors and designed and assessed its potential prediction model using multiple-linear regression equations in Ulsan area during the springtime from April to June, $2000{\sim}2004$. $O_3$ potential factors were selected by analyzing the relationship between meterological parameters and surface $O_3$ concentrations. In addition, cluster analysis (e.g., average linkage and K-means clustering techniques) was performed to identify three major synoptic patterns (e.g., $P1{\sim}P3$) for an $O_3$ potential prediction model. P1 is characterized by a presence of a low-pressure system over northeastern Korea, the Ulsan was influenced by the northwesterly synoptic flow leading to a retarded sea breeze development. P2 is characterized by a weakening high-pressure system over Korea, and P3 is clearly associated with a migratory anticyclone. The stepwise linear regression was performed to develop models for prediction of the highest 1-h $O_3$ occurring in the Ulsan. The results of the models were rather satisfactory, and the high $O_3$ simulation accuracy for $P1{\sim}P3$ synoptic patterns was found to be 79, 85, and 95%, respectively ($2000{\sim}2004$). The $O_3$ potential prediction model for $P1{\sim}P3$ using the predicted meteorological data in 2005 showed good high $O_3$ prediction performance with 78, 75, and 70%, respectively. Therefore the regression models can be a useful tool for forecasting of local $O_3$ concentration.

Application of Flow Network Models of SINDA/FLUIN $T^{TM}$ to a Nuclear Power Plant System Thermal Hydraulic Code

  • Chung, Ji-Bum;Park, Jong-Woon
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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    • pp.641-646
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    • 1998
  • In order to enhance the dynamic and interactive simulation capability of a system thermal hydraulic code for nuclear power plant, applicability of flow network models in SINDA/FLUIN $T^{™}$ has been tested by modeling feedwater system and coupling to DSNP which is one of a system thermal hydraulic simulation code for a pressurized heavy water reactor. The feedwater system is selected since it is one of the most important balance of plant systems with a potential to greatly affect the behavior of nuclear steam supply system. The flow network model of this feedwater system consists of condenser, condensate pumps, low and high pressure heaters, deaerator, feedwater pumps, and control valves. This complicated flow network is modeled and coupled to DSNP and it is tested for several normal and abnormal transient conditions such turbine load maneuvering, turbine trip, and loss of class IV power. The results show reasonable behavior of the coupled code and also gives a good dynamic and interactive simulation capabilities for the several mild transient conditions. It has been found that coupling system thermal hydraulic code with a flow network code is a proper way of upgrading simulation capability of DSNP to mature nuclear plant analyzer (NPA).

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고로내 열유동 현상의 수치해석 사례(I) (Numerical simulation of thermo-fluid flow in the blast furnace)

  • 진홍종;최상민
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회B
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    • pp.2038-2043
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    • 2007
  • Analysis of the internal state of the blast furnace is needed to predict and control the operating condition. Especially, it is important to develop modeling of blast furnace for predicting cohesive zone because shape of cohesive zone influences on overall operating condition of blast furnace such as gas flow, temperature distribution and chemical reactions. Because many previous blast furnace models assumed cohesive zone to be fixed, they can't evaluate change of cohesive zone shape by operation condition such as PCR, blast condition and production rate. In this study, an axi-symmetric 2-dimensional steady state model is proposed to simulate blast furnace process using the general purpose-simulation code. And Porous media is assumed for the gas flow and the potential flow for the solid flow. Velocity, pressure and temperature distribution for gas and solid are displayed as the simulation results. The cohesive zones are figured in 3 different operating conditions.

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인공신경망을 이용한 고속도로 기본구간 자유속도 추정모형개발 (Development of Free Flow Speed Estimation Model by Artificial Neural Networks for Freeway Basic Sections)

  • 강진구;장명순;김진태;김응철
    • 대한교통학회지
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    • 제22권3호
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    • pp.109-125
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    • 2004
  • 교통량 등의 도로외적인 요인을 배제한 도로의 물리적 특성이 미치는 영향으로 인하여 운전자의 주행행태가 변하는 것을 자유속도의 예측을 통하여 파악할 수 있다. 또한, 예측된 자유속도는 도로설계의 적정성 평가와 교통류 시뮬레이션 프로그램의 차량속로 입력자료에 이용될 수 있다. 기존의 자유속도 예측모형들이 이용해오던 선형 및 다중회귀분석과 달리 본 연구에서는 비선형적인 특성의 표현이 가능하고 여러 가지 기술적인 응용에 통용되고 있는 인공신경망을 이용하여 자유속도를 예측하고자 하였다. 고속도로 기본구간중 단곡선부를 대상으로 수집된 속도자료를 이용하여, 도로설계요소 중에서 평면 종단선형을 고려하고 횡단면 구성 요소의 일부를 반영한 결과 95% 신뢰수준에서 통계적으로 유의한 자유속도 예측모형을 개발할 수 있었다. 모형의 곡선 시점 중점속도의 RMSE는 6.68, 10.06이고 $R^2$는 0.77, 0.65로 기존에 개발되어있는 모형들과 비교하여 우수한 모형으로 분석되었다. 모형은 곡선 시점 중점에서의 속도특성을 곡선반경 등의 평면선형요소와 종단선형 요소별로 도출할 수 있으며, 연구결과는 현재 기본구간에 설계요소와 무관하게 일률 적용되는 자유속도를 도로설계요소와 관련하여 현실적으로 세분화하여 이용할 수 있는 근거를 제시하고, 나아가 설계일관성평가와 교통류 시뮬레이션에 적용할 수 있을 것으로 예상된다.

Correct Closure of the Left Atrial Appendage Reduces Stagnant Blood Flow and the Risk of Thrombus Formation: A Proof-of-Concept Experimental Study Using 4D Flow Magnetic Resonance Imaging

  • Min Jae Cha;Don-Gwan An;Minsoo Kang;Hyue Mee Kim;Sang-Wook Kim;Iksung Cho;Joonhwa Hong;Hyewon Choi;Jee-Hyun Cho;Seung Yong Shin;Simon Song
    • Korean Journal of Radiology
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    • 제24권7호
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    • pp.647-659
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    • 2023
  • Objective: The study was conducted to investigate the effect of correct occlusion of the left atrial appendage (LAA) on intracardiac blood flow and thrombus formation in patients with atrial fibrillation (AF) using four-dimensional (4D) flow magnetic resonance imaging (MRI) and three-dimensional (3D)-printed phantoms. Materials and Methods: Three life-sized 3D-printed left atrium (LA) phantoms, including a pre-occlusion (i.e., before the occlusion procedure) model and correctly and incorrectly occluded post-procedural models, were constructed based on cardiac computed tomography images from an 86-year-old male with long-standing persistent AF. A custom-made closed-loop flow circuit was set up, and pulsatile simulated pulmonary venous flow was delivered by a pump. 4D flow MRI was performed using a 3T scanner, and the images were analyzed using MATLAB-based software (R2020b; Mathworks). Flow metrics associated with blood stasis and thrombogenicity, such as the volume of stasis defined by the velocity threshold ($\left|\vec{V}\right|$ < 3 cm/s), surface-and-time-averaged wall shear stress (WSS), and endothelial cell activation potential (ECAP), were analyzed and compared among the three LA phantom models. Results: Different spatial distributions, orientations, and magnitudes of LA flow were directly visualized within the three LA phantoms using 4D flow MRI. The time-averaged volume and its ratio to the corresponding entire volume of LA flow stasis were consistently reduced in the correctly occluded model (70.82 mL and 39.0%, respectively), followed by the incorrectly occluded (73.17 mL and 39.0%, respectively) and pre-occlusion (79.11 mL and 39.7%, respectively) models. The surfaceand-time-averaged WSS and ECAP were also lowest in the correctly occluded model (0.048 Pa and 4.004 Pa-1, respectively), followed by the incorrectly occluded (0.059 Pa and 4.792 Pa-1, respectively) and pre-occlusion (0.072 Pa and 5.861 Pa-1, respectively) models. Conclusion: These findings suggest that a correctly occluded LAA leads to the greatest reduction in LA flow stasis and thrombogenicity, presenting a tentative procedural goal to maximize clinical benefits in patients with AF.

Development a numerical model of flow and contaminant transport in layered soils

  • Ahmadi, Hossein;Namin, Masoud M.;Kilanehei, Fouad
    • Advances in environmental research
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    • 제5권4호
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    • pp.263-282
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    • 2016
  • Contaminant transport in groundwater induces major threat and harmful effect on the environment; hence, the fate of the contaminant migration in groundwater is seeking a lot of attention. In this paper a two dimensional numerical flow and transport model through saturated layered soil is developed. Groundwater flow and solute transport has been simulated numerically using proposed model. The model implements the finite volume time splitting method to discretize the main equations. The performance, accuracy and efficiency of the out coming numerical models have been successfully examined by two test cases. The verification test cases consist of two-dimensional, groundwater flow and solute transport. The final purpose of this paper is to discuss and compare the shape of contaminant plume in homogeneous and heterogeneous media with different soil properties and control of solute transport using a zone for minimizing the potential of groundwater contamination; furthermore, this model leads to select the effective and optimum remedial strategies for cleaning the contaminated aquifers.

EXTENSION OF CFD CODES APPLICATION TO TWO-PHASE FLOW SAFETY PROBLEMS

  • Bestion, Dominique
    • Nuclear Engineering and Technology
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    • 제42권4호
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    • pp.365-376
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    • 2010
  • This paper summarizes the results of a Writing Group on the Extension of CFD codes to two-phase flow safety problems, which was created by the Group for Analysis and Management of Accidents of the Nuclear Energy Agency' Committee on the Safety of Nuclear Installations (NEA-CSNI). Two-phase CFD used for safety investigations may predict small scale flow processes, which are not seen by system thermalhydraulic codes. However, the two-phase CFD models are not as mature as those in the single phase CFD and potential users need some guidance for proper application. In this paper, a classification of various modelling approaches is proposed. Then, a general multi-step methodology for using two-phase-CFD is explained, including a preliminary identification of flow processes, a model selection, and a verification and validation process. A list of 26 nuclear reactor safety issues that could benefit from investigations at the CFD scale is identified. Then, a few issues are analyzed in more detail, and a preliminary state-of-the-art is proposed and the remaining gaps in the existing approaches are identified. Finally, guidelines for users are proposed.

충주댐 유역의 SWAT-K와 HSPF모형에 의한 수문성분 모의특성 비교 분석 (Comparison of SWAT-K and HSPF for Hydrological Components Modeling in the Chungju Dam Watershed)

  • 김남원;신아현;김철겸
    • 한국환경과학회지
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    • 제18권6호
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    • pp.609-619
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    • 2009
  • SWAT-K model is a modified version of the original SWAT, and is known to more accurately estimate the streamflows and pollutant loadings in Korean watersheds. In this study, its hydrological components were compared with those of HSPF in order to analyse the differences in total runoff including evapotranspiration(ET), surface flow, lateral flow and groundwater flow from the Chungju Dam watershed during $2000{\sim}2006$. Averaged annual runoff with SWAT-K overestimated by 1%, and HSPF underestimated it by 3% than observed runoff. Determination coefficients($R^2$) for observed and simulated daily streamflows by both the models were relatively good(0.80 by SWAT-K and 0.82 by HSPF). Potential ET and actual ET by HSPF were lower in winter, but similar or higher than those by SWAT-K. And though there were some differences in lateral and groundwater flows by two models because of the differences in hydrological algorithms, the results were to be reasonable. From the results, it was suggested that we should utilize a proper model considering the characteristic of study area and purposes of the model application because the simulated results from same input data could be different with models used. Also we should develop a novel model appropriate to Korean watersheds by enhancing limitations of the existing models in the future.

Recovery the Missing Streamflow Data on River Basin Based on the Deep Neural Network Model

  • Le, Xuan-Hien;Lee, Giha
    • 한국수자원학회:학술대회논문집
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    • 한국수자원학회 2019년도 학술발표회
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    • pp.156-156
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    • 2019
  • In this study, a gated recurrent unit (GRU) network is constructed based on a deep neural network (DNN) with the aim of restoring the missing daily flow data in river basins. Lai Chau hydrological station is located upstream of the Da river basin (Vietnam) is selected as the target station for this study. Input data of the model are data on observed daily flow for 24 years from 1961 to 1984 (before Hoa Binh dam was built) at 5 hydrological stations, in which 4 gauge stations in the basin downstream and restoring - target station (Lai Chau). The total available data is divided into sections for different purposes. The data set of 23 years (1961-1983) was employed for training and validation purposes, with corresponding rates of 80% for training and 20% for validation respectively. Another data set of one year (1984) was used for the testing purpose to objectively verify the performance and accuracy of the model. Though only a modest amount of input data is required and furthermore the Lai Chau hydrological station is located upstream of the Da River, the calculated results based on the suggested model are in satisfactory agreement with observed data, the Nash - Sutcliffe efficiency (NSE) is higher than 95%. The finding of this study illustrated the outstanding performance of the GRU network model in recovering the missing flow data at Lai Chau station. As a result, DNN models, as well as GRU network models, have great potential for application within the field of hydrology and hydraulics.

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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.