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A data-based model, such as an AAKR model is widely used for monitoring the drifts of sensors in nuclear power plants. However, since a training dataset and a test dataset for a data-based model cannot be constructed with the data from all the possible states, the model uncertainty cannot be good enough to represent the uncertainty of estimations. In fact, the errors of estimation grow much bigger if the incoming data come from inexperienced states. To overcome this limitation of the model uncertainty, a new measure of uncertainty for a data-based model is developed and the predicted uncertainty is introduced. The predicted uncertainty is defined in every estimation according to the incoming data. In this paper, the AAKR model is used as a data-based model. The predicted uncertainty is similar in magnitude to the model uncertainty when the estimation is made for the incoming data from the experienced states but it goes bigger otherwise. The characteristics of the predicted model uncertainty are studied and the usefulness is demonstrated with the pressure signals measured in the flow-loop system. It is expected that the predicted uncertainty can quite reduce the false alarm by using the variable threshold instead of the fixed threshold.

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권호기사 목록 테이블로 기사명, 저자명, 페이지, 원문, 기사목차 순으로 되어있습니다.
기사명 저자명 페이지 원문 목차
Establishment of the design stress intensity value for the plate-type fuel assembly using a tensile test Hyun-Jung Kim, Young-Wook Tahk, Hyunwoo Jun, Eui-Hyun Kong, Jae-Yong Oh, Jeong-Sik Yim p. 911-919

Measuring thermal conductivity and water suction for variably saturated bentonite Seok Yoon, Geon-Young Kim p. 1041-1048

Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break Jong Chull Jo, Jae-Jun Jeong, Frederick J. Moody p. 1029-1040

Research on non-uniform pressure pulsation of the diffuser in a nuclear reactor coolant pump Qiang Zhou, Hongkun Li, Lin Pei, Zuowen Zhong p. 1020-1028

Sentiment analysis of nuclear energy-related articles and their comments on a portal site in Rep. of Korea in 2010-2019 So Yun Jeong, Jae Wook Kim, Young Seo Kim, Han Young Joo, Joo Hyun Moon p. 1013-1019

Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants Jianfeng Shi, Anqi Hu, Fa Yu, Ying Cui, Ruobing Yang, Jinyang Zheng p. 1004-1012

Investigation of seismic responses of reactor vessel and internals for beyond-design basis earthquake using elasto-plastic time history analysis Sang-Jeong Lee, Eun-ho Lee, Changkyun Lee, No-Cheol Park, Youngin Choi, Changsik Oh p. 988-1003

Application of cohesive zone model to large scale circumferential through-wall and 360º surface cracked pipes under static and dynamic loadings Ji-Hee Moon, Youn-Young Jang, Nam-Su Huh, Do-Jun Shim, Kyoungsoo Park p. 974-987

Methodology of seismic-response-correlation-coefficient calculation for seismic probabilistic safety assessment of multi-unit nuclear power plants Seunghyun Eem, In-Kil Choi, Beomjoo Yang, Shinyoung Kwag p. 967-973

Estimation of radiostrontium, radiocesium and radiobarium transfer from arid soil to plant : a case study from Kuwait Abdulaziz Aba, Anfal Ismaeel, Omar Al-Boloushi p. 960-966

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Determining PGAA collimator plug design using Monte Carlo simulation A. Jalil, A. Chetaine, H. Amsil, K. Embarch, A. Benchrif, K. Laraki, H. Marah p. 942-948

Fracture simulation of SFR metallic fuel pin using finite element damage analysis method Hyun-Woo Jung, Hyun-Kyu Song, Yun-Jae Kim, Dong-Wook Jerng p. 932-941

Electrochemical corrosion study of helium ions implanted Zircaloy-4 in chloride media Mohsin Rafique, Atika Khan, Naveed Afzal, Ameeq Farooq, M. Imran p. 927-931

Neutron irradiation of alloy N and 316L stainless steel in contact with a molten chloride salt N. Dianne Bull Ezell, Stephen S. Raiman, J. Matt Kurley, Joel McDuffee p. 920-926

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Applications of online simulation supporting PWR operations Chunbing Wang, Qizhi Duan, Chao Zhang, Yipeng Fan p. 842-850

Design of the flexible switching controller for small PWR core power control with the multi-model Wenjie Zeng, Qingfeng Jiang, Shangmian Du, Tianyu Hui, Yinuo Liu, Sha Li p. 851-859

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(A) novel approach for analyzing the nuclear supply chain cyber-attack surface Shannon Eggers p. 879-887

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Sorption of Pd on illite, MX-80 bentonite and shale in Na-Ca-Cl solutions Jared Goguen, Andrew Walker, Joshua Racette, Justin Riddoch, Shinya Nagasaki p. 894-900

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On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX Bowen Xiao, Linfang Wei, Youqi Zheng, Bin Zhang, Hongchun Wu p. 732-740

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Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics Young Beom Jo, So-Hyun Park, Juryong Park, Eung Soo Kim p. 752-762

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Design and operation of the transparent integral effect test facility, URI-LO for nuclear innovation platform Kyung Mo Kim, In Cheol Bang p. 776-792

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참고문헌 (9건) : 자료제공( 네이버학술정보 )

참고문헌 목록에 대한 테이블로 번호, 참고문헌, 국회도서관 소장유무로 구성되어 있습니다.
번호 참고문헌 국회도서관 소장유무
1 H. Hashemian, On-line monitoring applications in nuclear power plants, Prog. Nucl. Energy 53 (2) (2011) 167-181. 미소장
2 J.B. Coble, R.M. Meyer, P. Ramuhalli, L.J. Bond, H. Hashemian, B. Shumaker, D. Cummins, A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants. No. PNNL-21687. Pacific Northwest National Lab(PNNL), 2012. Richland, WA USA. 미소장
3 J.W. Hines, R. Seibert, Technical Review of On-Line Monitoring Techniques for Performance Assessment (NUREG/CR-6895) Vol. 1. State-Of-The-Art, US Nuclear Regulatory Committee, 2006. 미소장
4 C.K. Williams, C.E. Rasmussen, Gaussian Processes for Machine Learning, MIT Press, 2006. 미소장
5 S. Lee, J. Chai, An enhanced prediction model for the on-line monitoring method using the Gaussian process regression, Journal of Mechanical Science and Technology. 33 (2019) 2249-2257, in re-view. 미소장
6 Yi Liu, Qing-Yang Wu, Junghui Chen, Active selection of informative data for sequential quality enhancement of soft sensor models with latent variables, Ind. Eng. Chem. Res. 56 (16) (2017) 4804-4817. 미소장
7 J.W. Hines, R. Seibert, Technical Review of On-Line Monitoring Techniques for Performance Assessment (NUREG/CR-6895) Vol. 2, in: Theoretical Issues, US Nuclear Regulatory Committee, 2008. May. 미소장
8 F. Di Maio, P. Baraldi, E. Zeo, R. Seraoui, Fault detection in nuclear power plants components by a combination of statistical methods, IEEE Trans. Reliab. 62 (4)(2013) 833-845. 미소장
9 N. Sairam, S. Mandal, Thermocouple Sensor Fault Detection Using AutoAssociative Kernel Regression and Generalized Likelihood Ratio Test., Computer, Electrical & Communication Engineering (ICCECE), 2016 International Conference on, IEEE, 2016, pp. 1-6. 미소장

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