• 제목/요약/키워드: Uncertainty evaluation

검색결과 894건 처리시간 0.026초

일사계 교정을 위한 불확실성 분석에 관한 연구 (A Study on the Uncertainty Analysis for Thermopile Pyranometer Calibrations)

  • 조덕기;전일수;전명석;강용혁;오정무
    • 한국태양에너지학회 논문집
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    • 제21권3호
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    • pp.25-32
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    • 2001
  • The major purpose of this paper is to develop an uncertainty estimate for the calibration of thermopile instruments used to measure solar radiation parameters. We briefly describe the solar radiation parameters most often measured, instrumentation, reference standards, and calibration techniques. The bulk of the paper describes elemental sources of error and their magnitude. We then apply a standard error analysis methodology to combine these elemental error estimates into a statement of total uncertainty for the instrument calibration factor. Our results allow one to evaluate the accuracy of a radiometric measurement using thermopile instrumentation in the light of the application, such as engineering test evaluation or for validation of theoretical models.

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국가교정검사기관(액체유량)의 측정불확도 평가 및 비교연구 (A Study on the Evaluation of Measurement Uncertainty for the National Calibration and Test Organizations (Liquid Flow))

  • 임기원
    • 설비공학논문집
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    • 제12권11호
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    • pp.1012-1019
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    • 2000
  • A proficiency test is one of programs which Korea Research Institute of Standards and Science(KRISS), as national metrology institute, is putting in operation for the mutual recognition arrangement. The Fluid Flow Group of KRISS evaluated the measurement capability for liquid flowmeter calibrator of the national calibration and test organizations. The uncertainty of national standard system was estimated in accordance with Guide to The Expression of Uncertainty in Measurement (ISO), and the turbine flowmeter, which was used for the round-robin test as a reference flowmeter, was characterized. The round-robin tests with the turbine flowmeter package were carried out in 1995 and 1999. The test results of the organizations and those of KRISS agreed within $\pm0.2$%. It is found thus that the organizations have the traceability of the national standard for liquid flow measurement.

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ERA 부분방전 측정시스템의 측정불확도개선 (Measurement uncertainty Improvement of ERA PD measuring system in teat laboratory)

  • 허종철;김위영;김석수;오창수;박정후
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 2006년도 제37회 하계학술대회 논문집 C
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    • pp.1509-1510
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    • 2006
  • ERA PD measuring system has been using for partial discharge evaluation of power appratus in test laboratories. So, the measurement uncertainty of PD measuring system (ERA), such as PD pulse calibrator rise and fall time, sacle factor(k) and linearity, transfer impedance etc, is very important factor of test result in test laboratory. In this paper, we describe tracebility and uncertainty improvement of PD measuring system in test laboratory based on IEC 60270.

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측정불확도를 고려한 배터리 교환형 전기버스용 접속기 접촉저항 평가에 관한 연구 (A Study of Contact Resistance Test Considered with Measurement Uncertainty for Electric Bus Couplers with Battery-Swapping System)

  • 김광민;이주
    • 조명전기설비학회논문지
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    • 제29권10호
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    • pp.60-64
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    • 2015
  • Many people think that Electric Vehicles(EVs) is the best method to resolve the problems of running out of fossil fuels. But EVs take long time for charging. So, EVs with battery swapping systems(EVBS) are developed to resolve this problem. Nonetheless, EVBS is not spreaded widely because the method of durability test in couplers is not defined. In this study, the evaluation method of durability test in couplers is defined by some standards and the measurement uncertainty is used to increase the reliability of EV couplers.

Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant

  • R.M. Nistor-Vlad;D. Dupleac;G.L. Pavel
    • Nuclear Engineering and Technology
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    • 제55권7호
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    • pp.2670-2677
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    • 2023
  • In the nuclear safety studies, a new trend refers to the evaluation of uncertainties as a mandatory component of best-estimate safety analysis which is a modern and technically consistent approach being known as BEPU (Best Estimate Plus Uncertainty). The major objectives of this study consist in performing a study of uncertainties/sensitivities of the major analysis results for a generic CANDU 6 Nuclear Power Plant during Station Blackout (SBO) progression to understand and characterize the sources of uncertainties and their effects on the key figure-of-merits (FOMs) predictions in severe accidents (SA). The FOMs of interest are hydrogen mass generation and event timings such as the first fuel channel failure time, beginning of the core disassembly time, core collapse time and calandria vessel failure time. The outcomes of the study, will allow an improvement of capabilities and expertise to perform uncertainty and sensitivity analysis with severe accident codes for CANDU 6 Nuclear Power Plant.