• Title/Summary/Keyword: Uncertainty modelling

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Stochastic modelling and lifecycle performance assessment of bond strength of corroded reinforcement in concrete

  • Chen, Hua-Peng;Nepal, Jaya
    • Structural Engineering and Mechanics
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    • v.54 no.2
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    • pp.319-336
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    • 2015
  • Life cycle performance of corrosion affected RC structures is an important and challenging issue for effective infrastructure management. The accurate condition assessment of corroded RC structures mainly depends on the effective evaluation of deterioration occurring in the structures. Structural performance deterioration caused by reinforcement corrosion is a complex phenomenon which is generally uncertain and non-decreasing. Therefore, a stochastic modelling such as the gamma process can be an effective tool to consider the temporal uncertainty associated with performance deterioration. This paper presents a time-dependent reliability analysis of corrosion affected RC structures associated bond strength degradation. Initially, an analytical model to evaluate cracking in the concrete cover and the associated loss of bond between the corroded steel and the surrounding cracked concrete is developed. The analytical results of cover surface cracking and bond strength deterioration are examined by experimental data available. Then the verified analytical results are used for the stochastic deterioration modelling, presented here as gamma process. The application of the proposed approach is illustrated with a numerical example. The results from the illustrative example show that the proposed approach is capable of assessing performance of the bond strength of concrete structures affected by reinforcement corrosion during their lifecycle.

Project Portfolio Evaluation Problem-Based on the Initial Construction and Periodic Revision Under Uncertainty (프로젝트 포트폴리오 평가문제 - 불확실성 하의 최초 구성 및 주기적 개정을 중심으로)

  • Nam, Jae-Deog;Ahn, Tae-Ho;Yun, Jeong-Sun
    • Journal of the military operations research society of Korea
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    • v.34 no.3
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    • pp.107-116
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    • 2008
  • This paper deals with modelling and introducing of the project portfolio construction and evaluation problem under uncertainty. The common way in industry of managing project portfolio is construction of initial portfolio considering uncertainties which exist inside and outside of portfolio, and periodic revision of portfolio due to the deviation from plans. In this paper, we introduce algorithm which reflecting the industrial common practice of initial planning and periodic revision. With this simulation method, probabilistic distribution of portfolio's performance in consideration can be found.

Variable Structure Control of an Electromagnetic Suspension Sys Using Adaptive Load Estimation (상전도 흡인식 자기 부상 시스템의 적응 제어 부하 예측기를 이용한 가변 구조 제어기 설계)

  • Lee, Sang-Bin;Lee, Jeong-Uk;Lee, In-Ho;Yoo, Ji-Yoon
    • Proceedings of the KIEE Conference
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    • 1997.07f
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    • pp.1982-1984
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    • 1997
  • In this paper, adaptive variable structure control is proposed for Electromagnetic Suspension(EMS). Although variable structure control shows excellent robustness to unstructured modelling uncertainty, such as flux leakage and saturation, it has several drawbacks that severely limit practical applicability such as high control activity and control chattering. To minimize these effects, the mass of the electromagnet and efficiency of levitation force are estimated on-line to reduce the range of system uncertainty. The effectiveness of the proposed control scheme is verified by experimental results using a 1.5kg electromagnet and DSP (TMS320C31).

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The uncertainty problem analysis of the engineering solution for prediction and estimation of the operating regime to design of gas- hydro-dynamic systems

  • Kartovitskiy, Lev;Tsipenko, Anton;Lee, Ji-Hyung
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2009.11a
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    • pp.459-468
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    • 2009
  • Analysis of the uncertainty to have engineering solution of gas-dynamic and hydrodynamic problems is based on the comparison the prospective engineering solution with experimental result. In this paper, the mathematical model to estimate heat flux along gas-dynamic channel wall and the solution sequence are shown. Statistical information and generalizing experimental characteristics about gas- and hydro-dynamic channels were applied to the mathematical model. As the results, it is possible to draw a conclusion that models of the integrated approach, using the averaged statistical data of generalizing characteristics for a turbulent flow, without consideration of the turbulent mechanism (characteristic pulsations), can predict a nominal operating regime for gas-dynamic and hydrodynamic systems. The probable deviation of operating regime for newly designed the gas-dynamic channel can achieve 20% from a regime predicted on a basis 1-D or 3-D modelling irrespective of a kind of used models.

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Reliability based seismic fragility analysis of bridge

  • Kia, M.;Bayat, M.;Emadi, A.;Kutanaei, S. Soleimani;Ahmadi, H.R
    • Computers and Concrete
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    • v.29 no.1
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    • pp.59-67
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    • 2022
  • In this paper, a reliability-based approach has been implemented to develop seismic analytical fragility curves of highway bridges. A typical bridge class of the Central and South-eastern United States (CSUS) region was selected. Detailed finite element modelling is presented and Incremental Dynamic Analysis (IDA) is used to capture the behavior of the bridge from linear to nonlinear behavior. Bayesian linear regression method is used to define the demand model. A reliability approach is implemented to generate the analytical fragility curves and the proposed approach is compared with the conventional fragility analysis procedure.

Sensitivity study of parameters important to Molten Salt Reactor Safety

  • Sarah Elizabeth Creasman;Visura Pathirana;Ondrej Chvala
    • Nuclear Engineering and Technology
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    • v.55 no.5
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    • pp.1687-1707
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    • 2023
  • This paper presents a molten salt reactor (MSR) design parameter sensitivity study using a nodal dynamic modelling methodology with explicitly modified point kinetics equation and Mann's model for heat transfer. Six parameters that can impact MSR safety are evaluated. A MATLAB-Simulink model inspired by Thorcon's 550MWth MSR is used for parameter evaluations. A safety envelope was formed to encapsulate power, maximum and minimum temperature, and temperature-induced reactivity feedback. The parameters are perturbed by ±30%. The parameters were then ranked by their subsequent impact on the considered safety envelope, which ranks acceptable parameter uncertainty. The model is openly available on GitHub.

PROJECTION OF TRAJECTORY FOR SUPPORTING UNCERTAINTY FUTURE TIME OF MOVING OBJECT

  • Won Ho-Gyeong;Jung Young Jin;Lee Yang Koo;Park Mi;Kim Hak-cheol;Ryu Keun Ho
    • Proceedings of the KSRS Conference
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    • 2005.10a
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    • pp.72-75
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    • 2005
  • Uncertainty of objects in Moving Object Database is a coherent property. It has been discussed in a lot of researches on modelling and query processing. The previous studies assume that uncertain future time is determined through utilizing recent speed and direction of vehicles. This method is simple and useful for estimating the time of the near future location. However, it is not appropriate when we estimate the time of the far future location. Therefore, in this paper, we propose a concept of planned route. It is used to estimate uncertain future time, which has to be located at a given point. If the route of an object is planned beforehand its locations are uncertainly distributed near that route. By a simple projection operation, the probability that a location lies in the planned route is increased. Moreover, we identify the future time of an object based on the speed for passing the route, which is offered via a website.

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MODFLOW or FEFLOW: A Case Study of Groundwater Model Selection for the Upper Waikato Catchment, New Zealand

  • Weir, Julian;Moore, Dr Catherine;Hadfield, John
    • Proceedings of the Korea Water Resources Association Conference
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    • 2011.05a
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    • pp.14-14
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    • 2011
  • Groundwater in the Waikatoregion is a valuable resource for agriculture, water supply, forestry and industries. The 434,000 ha study area comprises the upper Waikato River catchment from the outflow of Lake Taupo (New Zealand's largest lake) through to Lake Karapiro (a man-made hydro lake with high recreational value) (Figure 1). Water quality in the area is naturally high. However, there are indications that this quality is deteriorating as a result of land use intensification and deforestation. Compounding this concern for decision makers is the lag time between land use changes and the realisation of effects on groundwater and surface water quality. It is expected that the effects of land use changes have not yet fully manifested, and additional intensification may take decadesto fully develop, further compounding the deterioration. Consequently, Environment Waikato (EW) have proposed a programme of work to develop a groundwater model to assist managing water quality and appropriate policy development within the catchment. One of the most important and critical decisions of any modelling exercise is the choice of the modelling platform to be used. It must not inhibit future decision making and scenario exploration and needs to allow as accurate representation of reality as feasible. With this in mind, EW requested that two modelling platforms, MODFLOW/MT3DMS and FEFLOW, be assessed for their ability to deliver the long-term modelling objectives for this project. The two platforms were compared alongside various selection criteria including complexity of model set-up and development, computational burden, ease and accuracy of representing surface water-groundwater interactions, precision in predictive scenarios and ease with which the model input and output files could be interrogated. This latter criteria is essential for the thorough assessment of predictive uncertainty with third-party software, such as PEST. This paper will focus on the attributes of each modelling platform and the comparison of the two approaches against the key criteria in the selection process. Primarily due to the ease of handling and developing input files and interrogating output files, MODFLOW/MT3DMS was selected as the preferred platform. Other advantages and disadvantages of the two modelling platforms were somewhat balanced. A preliminary regional groundwater numerical model of the study area was subsequently constructed. The model simulates steady state groundwater and surface water flows using MODFLOW and transient contaminant transport with MT3DMS, focussing on nitrate nitrogen (as a conservative solute). Geological information for this project was provided by GNS Science. Professional peer review was completed by Dr. Vince Bidwell (of Lincoln Environmental).

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Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests

  • Guo, Hui;Jin, Xin;Huo, Xingkai;Gu, Hanyang;Wu, Haicheng
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3888-3896
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    • 2022
  • Nuclear data is the basis of reactor physics analysis. This paper aim at studying the influence of major evaluated nuclear data libraries, CENDL-3.2, ENDF/B-VIII.0, JEFF-3.3, and JENDL-4.0u, on the neutronics modelling of CEFR start-up tests. Results show these four libraries have a good performance and consistency in the modelling CEFR start-up tests. The JEFF-3.3 results exhibit only an 8 pcm keff difference with the measurement. The difference in criticality is decomposed by nuclide, which shows the large overestimation of CENDL-3.2 is mainly from the cross-section of 52Cr. Except for few cases, the calculation results are within 1σ of measurement uncertainty in control rod worth, sodium void reactivity, temperature reactivity, and subassembly swap reactivity. In the evaluation of axial and radial reaction distribution, there are about 65% of relative errors that are less than 5% and 82% of relative errors that are less than 10%.

Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

  • Guo, Hui;Huo, Xingkai;Feng, Kuaiyuan;Gu, Hanyang
    • Nuclear Engineering and Technology
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    • v.54 no.10
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    • pp.3897-3908
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    • 2022
  • High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project on "Neutronics Benchmark of CEFR Start-Up Tests" offers valuable data for the qualification of nuclear data libraries and neutronics codes. This paper focuses on the verification and validation of the CEFR start-up modelling using OpenMC Monte-Carlo code against the experimental measurements. The OpenMC simulation results agree well with the measurements in criticality, control rod worth, sodium void reactivity, temperature reactivity, subassembly swap reactivity, and reaction distribution. In feedback coefficient evaluations, an additional state method shows high consistency with lower uncertainty. Among 122 relative errors in the benchmark of the distribution of nuclear reaction, 104 errors are less than 10% and 84 errors are less than 5%. The results demonstrate the high reliability of OpenMC for its application in fast reactor simulations. In the companion paper, the influence of cross-section libraries is investigated using neutronics modelling in this paper.