• Title/Summary/Keyword: Uncertainty evaluation

검색결과 892건 처리시간 0.029초

Evaluation of Failure Probability for Planar Failure Using Point Estimate Method (점추정법을 이용한 평면파괴의 파괴확률 신정)

  • Park, Hyuck-Jin
    • Tunnel and Underground Space
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    • 제12권3호
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    • pp.189-197
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    • 2002
  • In recent years, the probabilistic analysis has been used in rock slope engineering. This is because uncertainty is pervasive in rock slope engineering and most geometric and geotechnical parameters of discontinuity and rock masses are involved with uncertainty. Whilst the traditional deterministic analysis method fails to properly deal with uncertainty, the probabilistic analysis has advantages quantifying the uncertainty in parameters. As a probabilistic analysis method, the Monte Carlo simulation has been used commonly. However, the Monte Carlo simulation requires many repeated calculations and therefore, needs much effort and time to calculate the probability of failure. In contrast, the point estimate method involves a simple calculation with moments for random variables. In this study the probability of failure in rock slope is evaluated by the point estimate method and the results are compared to the probability of failure obtained by Monte Carlo simulation method.

Measurements of Two-dimensional Gratings Using a Metrological Atomic Force Microscope with Uncertainty Evaluation

  • Kim, Jong-Ahn;Kim, Jae-Wan;Kang, Chu-Shik;Eom, Tae-Bong
    • International Journal of Precision Engineering and Manufacturing
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    • 제9권2호
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    • pp.18-22
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    • 2008
  • The pitch and orthogonality of two-dimensional (2-D) gratings were measured using a metrological atomic force microscope (MAFM), and the measurement uncertainty was analyzed. Gratings are typical standard devices for the calibration of precision microscopes, Since the magnification and orthogonality in two perpendicular axes of microscopes can be calibrated simultaneously using 2-D gratings, it is important to certify the pitch and orthogonality of such gratings accurately for nanometrology. In the measurement of 2-D gratings, the MAFM can be used effectively for its nanometric resolution and uncertainty, but a new measurement scheme is required to overcome limitations such as thermal drift and slow scan speed. Two types of 2-D gratings with nominal pitches of 300 and 1000 nm were measured using line scans to determine the pitch measurement in each direction. The expanded uncertainties (k = 2) of the measured pitch values were less than 0.2 and 0.4 nm for each specimen, and the measured orthogonality values were less than $0.09^{\circ}$ and $0.05^{\circ}$, respectively. The experimental results measured using the MAFM and optical diffractometer agreed closely within the expanded uncertainty of the MAFM. We also propose an additional scheme for measuring 2-D gratings to increase the accuracy of calculated peak positions, which will be the subject of future study.

Evaluation of Uncertainty Sources in Temperature Measurement Using Platinum Resistance Thermometer Caused by Temperature Gradient in Furnace and Sealed-type Freezing Point Cells (전기로 및 봉입형 응고점 셀 내의 온도구배가 미치는 표준백금저항온도계 온도측정의 불확도 요소 평가)

  • Kang, Kee-Hoon;Gam, Kee-Sool;Kim, Yong-Gyoo;Song, Chang-Ho
    • Journal of Sensor Science and Technology
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    • 제13권6호
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    • pp.411-416
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    • 2004
  • In the international temperature scale of 1990 (ITS-90), standard platinum resistance thermometer (SPRT) is a defining standard thermometer used in the temperature range from 13.8033 K to $961^{\circ}C$. Uncertainty of SPRT is about several mK and uncertainty of defining fixed points of the ITS-90 which is used for calibrating SPRT is about several tenth of mK. Above $0^{\circ}C$. the defining fixed points are gallium melting point and indium, tin, zinc, aluminium and silver freezing points which are all realized using an electric furnace or a liquid bath. To realize freezing point of tin ($231.928^{\circ}C$) and zinc ($419.527^{\cir}C$), two 3-zone furnaces which have 3 electric heaters were manufactured. Temperature gradient of the constructed furnaces were tested. Uncertainty caused by temperature gradient of furnace and immersion effect of SPRT in the sealed-type freezing point cells were evaluated 0.038 mK for tin freezing point and 0.036 mK for zinc freezing point.

Welfare Evaluation in Contingent Valuation under Alternative Approaches for Incorporating Respondent Uncertainty (지불의사 유도방식에 따른 온실가스 배출 감축의 편익 비교 분석)

  • Kim, Chung-Sil;Lee, Sang-Ho
    • Journal of Environmental Policy
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    • 제8권3호
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    • pp.163-180
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    • 2009
  • This study attempts to investigate the preference uncertainty of respondents involved in stating their Willingness to Pay (WTP). For the Contingent Valuation Method (CVM) survey, we employed two approaches using two split samples. The respondents of one sample were given the opportunity to express intensity of preference through Multi-bounded Discrete Choice (MBDC) WTP questions, while those in the other sample were given Dichotomous Choice (DC) WTP questions. By incorporating the two elicited degrees of preference uncertainty into examining the WTP responses, we compared the two approaches. In comparing the DC model with the MBDC model, the mean WTP for the DC model was similar to PRYES in the MBDC Model. We concluded that the MBDC model estimates the various mean WTP while considering the preference uncertainty.

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Study on the estimation of uncertainty for the air-borne noise measurements in a naval ship (함정 내 소음 평가를 위한 불확도 추정 기법 연구)

  • Kim, Seong-Yong
    • Journal of Advanced Marine Engineering and Technology
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    • 제38권4호
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    • pp.396-402
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    • 2014
  • The measurement of air-borne noise in a naval ship is a crucial element. Because the noise in a naval ship interferes with a communication between crews and finally it causes to reduce the combat power. Thus, most of newly built ships have to satisfy the criteria of air-borne noise in the stage of delivery of a naval ship. In order to evaluate success or failure of criteria, uncertainty of the measurement should be considered. This study introduces the test method for the measurement of the air-borne noise in a naval ship and is concerned with the evaluation of uncertainty. The uncertainty results which was from the measurement of air-borne noise in 7 naval ships newly built satisfy the error tolerance(2dB). Therefore, it is need to reduce the error tolerance for the reliable measurement result.

Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks

  • Ho Jin Park;Jin Young Cho
    • Nuclear Engineering and Technology
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    • 제55권4호
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    • pp.1563-1570
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    • 2023
  • In this study, a DeCART/MIG uncertainty quantification (UQ) analysis code system with a multicorrelated cross section stochastic sampling (S.S.) module was established and verified through the UAM (Uncertainty Analysis in Modeling) and the BEAVRS (Benchmark for Evaluation And Validation of Reactor Simulations) benchmark calculations. For the S.S. calculations, a sample of 500 DeCART multigroup cross section sets for two major actinides, i.e., 235U and 238U, were generated by the MIG code and covariance data from the ENDF/B-VII.1 evaluated nuclear data library. In the three pin problems (i.e. TMI-1, PB2, and Koz-6) from the UAM benchmark, the uncertainties in kinf by the DeCART/MIG S.S. calculations agreed very well with the sensitivity and uncertainty (S/U) perturbation results by DeCART/MUSAD and the S/U direct subtraction (S/U-DS) results by the DeCART/MIG. From these results, it was concluded that the multi-group cross section sampling module of the MIG code works correctly and accurately. In the BEAVRS whole benchmark problems, the uncertainties in the control rod bank worth, isothermal temperature coefficient, power distribution, and critical boron concentration due to cross section uncertainties were calculated by the DeCART/MIG code system. Overall, the uncertainties in these design parameters were less than the general design review criteria of a typical pressurized water reactor start-up case. This newly-developed DeCART/MIG UQ analysis code system by the S.S. method can be widely utilized as uncertainty analysis and margin estimation tools for developing and designing new advanced nuclear reactors.

Sensitivity Analysis in the Prediction of Coastal Erosion due to Storm Events: case study-Ilsan beach (태풍 기인 연안침식 예측의 불확실성 분석: 사례연구-일산해변)

  • Son, Donghwi;Yoo, Jeseon;Shin, Hyunhwa
    • Journal of Coastal Disaster Prevention
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    • 제6권3호
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    • pp.111-120
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    • 2019
  • In coastal morphological modelling, there are a number of input factors: wave height, water depth, sand particle size, bed friction coefficients, coastal structures and so forth. Measurements or estimates of these input data may include uncertainties due to errors by the measurement or hind-casting methods. Therefore, it is necessary to consider the uncertainty of each input data and the range of the uncertainty during the evaluation of numerical results. In this study, three uncertainty factors are considered with regard to the prediction of coastal erosion in Ilsan beach located in Ilsan-dong, Ulsan metropolitan city. Those are wave diffraction effect of XBeach model, wave input scenario and the specification of the coastal structure. For this purpose, the values of mean wave direction, significant wave height and the height of the submerged breakwater were adjusted respectively and the followed numerical results of morphological changes are analyzed. There were erosion dominant patterns as the wave direction is perpendicular to Ilsan beach, the higher significant wave height, and the lower height of the submerged breakwater. Furthermore, the rate of uncertainty impacts among mean wave direction, significant wave height and the height of the submerged breakwater are compared. In the study area, the uncertainty influence by the wave input scenario was the largest, followed by the height of the submerged breakwater and the mean wave direction.

Evaluation by Fuzzy Checklist

  • Kim, Kuk
    • Journal of Korean Institute of Industrial Engineers
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    • 제14권1호
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    • pp.57-71
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    • 1988
  • Checklist method is rapid and comprehensive to evaluate in practice. Check items are commonly rated by subjective utility function; i.e., evaluator's significant judgment. Since human judgment includes fuzziness (vagueness) inherently in spite of its significance, fuzzy set theory is useful in this case. The paper illustrates a evaluation method using fuzzy checklist where check items are rated as fuzzy numbers. Pairwise comparison data is used to determine the weights of check items, since it has comparative advantage for human's fuzzy judgment. Sample of BASIC program is provided for microcomputer. When uncertainty is due to subjectivity or imprecision of data, this method can be applied to practical problems widely.

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SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION

  • Cho, Nam-Zin;Chang, Jong-Hwa
    • Nuclear Engineering and Technology
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    • 제41권4호
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    • pp.381-390
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    • 2009
  • This article provides selects of outstanding problems in computational neutron transport, with some suggested approaches thereto, as follows: i) ray effect in discrete ordinates method, ii) diffusion synthetic acceleration in strongly heterogeneous problems, iii) method of characteristics extension to three-dimensional geometry, iv) fission source and $k_{eff}$ convergence in Monte Carlo, v) depletion in Monte Carlo, vi) nuclear data evaluation, and vii) uncertainty estimation, including covariance data.

Consideration for Heat Exchanger Performance Evaluation with reduced spend fuel pool heat due to the long-term over-haul maintenance (장기 예방정비로 인한 사용후연료저장조 열원 감소가 열교환기 성능평가에 미치는 영향 고찰)

  • Park, Chan;Lee, Sung Ho
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • 제16권1호
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    • pp.56-64
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    • 2020
  • The safety related heat exchangers have been evaluated for their performance during the operation of the nuclear power plant. The evaluation program for the safety related heat exchanger was developed in 2010 and used by KHNP based on EPRI TR-10739 algorithms. The spend fuel pool heat exchanger is one of the safety related heat exchanger in the nuclear power plant and also evaluated for their performance. Recently the performance evaluation for the spend fuel pool heat exchanger was not available because of the decreased heat in the spend fuel pool due to the long term overhaul. This paper analyzes the main cause of evaluation failure in the evaluation process and suggests the criteria for the heat exchanger performance evaluation during the long term overhaul.