An Estimation Method For Bias Error Of Measurements By Utilizing Process Data, An Incidence Matrix And A Reference Instrument For Data Validation And Reconciliation

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
A. Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
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引用次数: 0

Abstract

With further applications of AI, IoT, and digital twin technology to plant operation and maintenance, it is becoming increasingly important to ensure data reliability. Data validation and reconciliation (DVR) represents one promising technique to ensure data reliability by minimizing the uncertainty of measurements based on statistics. DVR has been widely applied to nuclear power electrical generation plants in Europe and the United States in recent years. The most important input for DVR analysis is measurement uncertainty. In Japan, performance management of nuclear power plants is often done by measuring condensate flow rate. While the uncertainty of other flowmeters is handled by the JIS standard, the condensate flowmeter is specially calibrated every few cycles. This leads to reduction of effectiveness of DVR analysis due to variations in measurement uncertainty management. To overcome this issue, we propose an estimation method for measurement uncertainty by utilizing process data, an incidence matrix between sensors, and a reference instrument. The conventional method proposed in the previous study only treats the random error. The proposed method quantitatively estimates not only random error but also bias error by considering the uncertainty of the reference instrument. Using several benchmark problems, we found that the proposed method was applicable to various flow conditions, including physically fluctuating flow such as that observed in the feedwater flow in nuclear power plants. We anticipate that the proposed method will promote use of DVR analysis in nuclear power plants in Japan.
一种利用过程数据、关联矩阵和参考仪器对测量偏差误差进行估计的方法
随着人工智能、物联网和数字孪生技术在工厂运维中的进一步应用,确保数据可靠性变得越来越重要。数据验证和核对(DVR)是一种很有前途的技术,它通过最小化基于统计的测量的不确定性来确保数据的可靠性。近年来,DVR在欧美国家的核电发电厂得到了广泛的应用。DVR分析最重要的输入是测量不确定度。在日本,核电站的性能管理通常是通过测量冷凝水流量来完成的。虽然其他流量计的不确定度由JIS标准处理,但冷凝水流量计每隔几个周期进行专门校准。由于测量不确定度管理的变化,这导致DVR分析的有效性降低。为了克服这个问题,我们提出了一种利用过程数据、传感器之间的关联矩阵和参考仪器来估计测量不确定度的方法。以往研究中提出的传统方法只处理随机误差。该方法在考虑参考仪器不确定度的基础上,对随机误差和偏置误差进行了定量估计。通过几个基准问题,我们发现所提出的方法适用于各种流动条件,包括物理波动的流动,如在核电站给水流动中观察到的流动。我们期望所提出的方法将促进DVR分析在日本核电站的应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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