REGULARIZATION OF FEEDWATER FLOW RATE EVALUATION FOR VENTURI METER FOULING PROBLEM IN NUCLEAR POWER PLANTS

ANDREI V. GRIBOK; IBRAHIM K. ATTIEH; J. WESLEY HINES

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REGULARIZATION OF FEEDWATER FLOW RATE EVALUATION FOR VENTURI METER FOULING PROBLEM IN NUCLEAR POWER PLANTS

机译：核电站文特米泄漏问题的进水流量评估调整。

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Inferential sensing is a method that can be used to evaluate parameters of a physical system based on a set of measurements related to these parameters. The most common method of inferential sensing uses mathemati- cal models to infer a parameter value from correlated sensor values. However, since inferential sensing is an inverse problem, it can produce inconsistent results due to minor perturbations in the data.

机译：推理感测是一种可用于基于与这些参数有关的一组测量来评估物理系统的参数的方法。推论感测的最常用方法是使用数学模型从相关的传感器值中推论参数值。但是，由于推理是一个反问题，因此由于数据中的微小扰动，它可能会产生不一致的结果。

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《Nuclear Technology》 |2001年第1期|p.3-14|共12页
作者
ANDREI V. GRIBOK; IBRAHIM K. ATTIEH; J. WESLEY HINES;
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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类原子能技术;
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1. Stochastic regularization of feedwater flow rate evaluation for the venturi meter fouling problem in nuclear power plants [J] . Andrei V. Gribok, Ibrahim K. Attieh, J. Wesley Hines, Inverse problems in engineering . 2001,第6期

机译：核电站文丘里计结垢问题的给水流量评估的随机正则化
2. Estimation of the flow profile correction factor of a transit-time ultrasonic flow meter for the feedwater flow measurement in a nuclear power plant [J] . Jae Cheon Jung, Poong Hyun Seong IEEE Transactions on Nuclear Science . 2005,第3期

机译：用于核电站给水流量测量的渡越时间超声波流量计的流量剖面校正因子的估算
3. Flow analysis and flow-induced vibration evaluation for low-pressure feedwater heater of a nuclear power plant [J] . Chin-Cheng Huang, Jen-Sheng Hsieh, Pay-Chung Chen, International Journal of Pressure Vessels and Piping . 2008,第9期

机译：核电站低压给水加热器的流量分析和流致振动评估
4. An Optimum Solutions for Venturi Used for Main Feedwater Flowrate Measurement in Nuclear Power Plant [C] . Zong-Jian Shangguan, Hua-Tong Wei, Lin Guo International symposium on software reliability, industrial safety, cyber security and physical protection of nuclear power plant . 2020

机译：用于核电站主要进给水流量测量的Venturi的最佳解决方案
5. Parameters influencing Flow-Accelerated Corrosion (FAC) in the secondary side of nuclear power plants [D] . Khatibi, Mahsa 2010

机译：影响核电厂二次侧流动加速腐蚀（FAC）的参数
6. A novel integrated approach for the hazardous radioactive dust source terms estimation in future nuclear fusion power plants [O] . L.A. Poggi, A. Malizia, J.F. Ciparisse, 2016

机译：未来核聚变电厂中有害放射性粉尘源项估算的一种新型综合方法
7. Regularization Of Feedwater Flow Rate Evaluation For Venturi Meter Fouling Problem In Nuclear Power Plants. [O] . Andrei V. Gribok, Ibrahim Attieh, J. Wesley Hines, 1999

机译：核电站文丘里流量计结垢问题的给水流量评估的正则化。
8. In-Flow Technology for the Determination of Sr-90 Concentrations in Nuclear Power Plants. Swedish Nuclear Power Inspectorate - Project B 46/81, Part 1 [R] . Dissing, E. 1982

机译：流动技术测定核电厂sr-90浓度。瑞典核电监察局 - 项目B 46/81，第1部分

REGULARIZATION OF FEEDWATER FLOW RATE EVALUATION FOR VENTURI METER FOULING PROBLEM IN NUCLEAR POWER PLANTS

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