Robust on-line diagnosis tool for the early accident detection in nuclear power plants

被引:36
作者
Tolo, Silvia [1 ]
Tian, Xiange [2 ]
Bausch, Nils [2 ]
Becerra, Victor [2 ]
Santhosh, T., V [3 ]
Vinod, G. [3 ]
Patelli, Edoardo [1 ]
机构
[1] Univ Liverpool, Inst Risk & Uncertainty, Liverpool, Merseyside, England
[2] Univ Portsmouth, Sch Engn, Portsmouth, Hants, England
[3] Bhabha Atom Res Ctr, Reactor Safety Div, Mumbai, Maharashtra, India
基金
英国工程与自然科学研究理事会;
关键词
LOCA; Neural networks; Pattern recognition; Bayesian statistics; Fault diagnostics; On-line condition monitoring; ARTIFICIAL NEURAL-NETWORK; FAULT-DIAGNOSIS; PREDICTION; SYSTEM; MODEL; IDENTIFICATION; OPERATIONS; ACCURACY; FUEL;
D O I
10.1016/j.ress.2019.02.015
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Any loss of coolant accident mitigation strategy is necessarily bound by the promptness of the break detection as well as the accuracy of its diagnosis. The availability of on-line monitoring tools is then crucial for enhancing safety of nuclear facilities. The requirements of robustness and short latency implied by the necessity for fast and effective actions are undermined by the challenges associated with break prediction during transients. This study presents a novel approach to tackle the challenges associated with the on-line diagnostics of loss of coolant accidents and the limitations of the current state of the art. Based on the combination of a set of artificial neural network architectures through the use of Bayesian statistics, it allows to robustly absorb different sources of uncertainty without requiring their explicit characterization in input. It provides the quantification of the output confidence bounds but also enhances of the model response accuracy. The implemented methodology allows to relax the need for model selection as well as to limit the demand for user-defined analysis parameters. A numerical case-study entailing a 220 MWe heavy-water reactor is analysed in order to test the efficiency of the developed computational tool.
引用
收藏
页码:110 / 119
页数:10
相关论文
共 38 条
[21]  
Onwubolu G., 2016, GMDH METHODOLOGY IMP, DOI [10.1142/p982, DOI 10.1142/P982]
[22]  
Oparaji U, 2017, P 2 INT C UNC QUANT
[23]   Robust artificial neural network for reliability and sensitivity analyses of complex non-linear systems [J].
Oparaji, Uchenna ;
Sheu, Rong-Jiun ;
Bankhead, Mark ;
Austin, Jonathan ;
Patelli, Edoardo .
NEURAL NETWORKS, 2017, 96 :80-90
[24]   Using a multi-state recurrent neural network to optimize loading patterns in BWRs [J].
Ortiz, JJ ;
Requena, I .
ANNALS OF NUCLEAR ENERGY, 2004, 31 (07) :789-803
[25]  
Patelli E., 2016, HDB UNCERTAINTY QUAN, P169, DOI [10.1007/978-3-319-11259-6_59-1, DOI 10.1007/978-3-319-11259-6_59-1]
[26]   EBaLM-THP - A neural network thermohydraulic prediction model of advanced nuclear system components [J].
Ridluan, Artit ;
Manic, Milos ;
Tokuhiro, Akira .
NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (02) :308-319
[27]   LEARNING REPRESENTATIONS BY BACK-PROPAGATING ERRORS [J].
RUMELHART, DE ;
HINTON, GE ;
WILLIAMS, RJ .
NATURE, 1986, 323 (6088) :533-536
[28]   Uncertainty analysis of a large break loss of coolant accident in a pressurized water reactor using non-parametric methods [J].
Sanchez-Saez, F. ;
Sanchez, A. I. ;
Villanueva, J. F. ;
Carlos, S. ;
Martorell, S. .
RELIABILITY ENGINEERING & SYSTEM SAFETY, 2018, 174 :19-28
[29]   Diagnostic system for identification of accident scenarios in nuclear power plants using artificial neural networks [J].
Santosh, T. V. ;
Srivastava, A. ;
Rao, V. V. S. Sanyasi ;
Ghosh, A. K. ;
Kushwaha, H. S. .
RELIABILITY ENGINEERING & SYSTEM SAFETY, 2009, 94 (03) :759-762
[30]  
Shan J, 1999, NUCL POWER ENG, V20, P182