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Elsamahy M, Nagla TF, Abdel-Rahman MAE. Pattern Recognition–Based Technique for Control Rod Position Identification in Pressurized Water Reactors. NUCL TECHNOL 2020. [DOI: 10.1080/00295450.2020.1792742] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
Affiliation(s)
| | - Tarek F. Nagla
- Alexandria University, Nuclear Engineering Department, Faculty of Engineering, Alexandria, Egypt
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Kim JM, Lee G, Lee C, Lee SJ. Abnormality diagnosis model for nuclear power plants using two-stage gated recurrent units. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.02.002] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Comparative study of application of different supervised learning methods in forecasting future states of NPPs operating parameters. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.04.031] [Citation(s) in RCA: 18] [Impact Index Per Article: 3.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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A study on the robustness of neural network models for predicting the break size in LOCA. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.07.004] [Citation(s) in RCA: 15] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Research on intelligent fault diagnosis method for nuclear power plant based on correlation analysis and deep belief network. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.06.003] [Citation(s) in RCA: 54] [Impact Index Per Article: 9.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Alamaniotis M, Cappelli M. Intelligent Identification of Boiling Water Reactor State Utilizing Relevance Vector Regression Models. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2018. [DOI: 10.1115/1.4037203] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Modernization of reactor instrumentation and control systems is mainly characterized by the transition from analog to digital systems, expressed by replacement of hardware equipment with new software-driven devices. Digital systems may share intelligence capabilities where except for measuring and processing information may also make decisions. State identification systems are systems that process the measurements taken over operational variables and output the state of the reactor. This paper frames itself in the area of control systems applied to state identification of boiling water reactors (BWRs). It presents a methodology that utilizes machine learning tools, and more specifically, a set of relevance vector machines (RVMs) in order to process the incoming signals and identify the state of the BWR in real time. The proposed methodology is comprised of two stages: in the first stage, each RVM identifies the state of the BWR, while the second stage collects the RVM outputs and decides about the real state of the reactor adopting majority voting. The proposed methodology is tested on a set of real-world BWR data taken from the experimental FIX-II facility for recognizing various BWR loss-of-coolant accidents (LOCAs) as well as normal states. Results exhibit the efficiency of the methodology in correctly identifying the correct state of the BWR while promoting real time identification by providing fast responses. However, a strong dependence of identification performance on the form of kernel functions is also concluded.
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Affiliation(s)
- Miltiadis Alamaniotis
- Applied Intelligent Systems Laboratory, School of Nuclear Engineering, Purdue University, 400 Central Dr., West Lafayette, IN 47907 e-mail:
| | - Mauro Cappelli
- ENEA UTFISST-MEPING-Casaccia Research Center, Via Anguillarese, Rome 301-00123, Italy e-mail:
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Saghafi M, Ghofrani MB. Accident management support tools in nuclear power plants: A post-Fukushima review. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.06.006] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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