Sensor response monitoring in pressurized water reactors using time series modeling

B. Upadhyaya, T. Kerlin
{"title":"Sensor response monitoring in pressurized water reactors using time series modeling","authors":"B. Upadhyaya, T. Kerlin","doi":"10.1109/CDC.1978.268053","DOIUrl":null,"url":null,"abstract":"Random data analysis in nuclear power reactors for purposes of process surveillance, pattern recognition and monitoring of temperature, pressure, flow and neutron sensors has gained increasing attention in view of their potential for helping to ensure safe plant operation. In this paper, application of autoregressive moving-average (ARMA) time series modeling for monitoring temperature sensor response charactersitics is presented. The ARMA model is used to estimate the step and ramp response of the sensors and the related time constant and ramp delay time. The ARMA parameters are estimated by a two-stage algorithm in the spectral domain. Results of sensor testing for an operating pressurized water reactor are presented. Since the estimation depends on the random signal characteristics, there are cases where the noise analysis approach fails to predict sensor characteristics accurately. In general, the approach is useful for sensor monitoring schemes, rather than to predict a quantitative value of the sensor response.","PeriodicalId":375119,"journal":{"name":"1978 IEEE Conference on Decision and Control including the 17th Symposium on Adaptive Processes","volume":"98 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"1978 IEEE Conference on Decision and Control including the 17th Symposium on Adaptive Processes","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/CDC.1978.268053","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

Random data analysis in nuclear power reactors for purposes of process surveillance, pattern recognition and monitoring of temperature, pressure, flow and neutron sensors has gained increasing attention in view of their potential for helping to ensure safe plant operation. In this paper, application of autoregressive moving-average (ARMA) time series modeling for monitoring temperature sensor response charactersitics is presented. The ARMA model is used to estimate the step and ramp response of the sensors and the related time constant and ramp delay time. The ARMA parameters are estimated by a two-stage algorithm in the spectral domain. Results of sensor testing for an operating pressurized water reactor are presented. Since the estimation depends on the random signal characteristics, there are cases where the noise analysis approach fails to predict sensor characteristics accurately. In general, the approach is useful for sensor monitoring schemes, rather than to predict a quantitative value of the sensor response.
基于时间序列模型的压水堆传感器响应监测
为了过程监视、模式识别和监测温度、压力、流量和中子传感器而对核动力反应堆进行的随机数据分析,由于其有助于确保工厂安全运行的潜力,已受到越来越多的关注。本文介绍了自回归移动平均(ARMA)时间序列模型在温度传感器响应特性监测中的应用。利用ARMA模型估计传感器的阶跃和斜坡响应以及相关的时间常数和斜坡延迟时间。在谱域采用两阶段算法估计ARMA参数。介绍了在役压水堆传感器的测试结果。由于估计依赖于随机信号的特性,因此存在噪声分析方法不能准确预测传感器特性的情况。一般来说,该方法对传感器监测方案有用,而不是预测传感器响应的定量值。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信