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Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks
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Outgoing claims: the papers this work cites, builds on, or argues with.
inferredcites →https://doi.org/10.1006/ijhc.1973.0303openalex-snapshot
An Experiment in Linguistic Synthesis with a Fuzzy Logic Controller
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Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks
inferredcites →https://doi.org/10.1016/j.nucengdes.2004.06.007openalex-snapshot
Estimation of break location and size for loss of coolant accidents using neural networks
inferredcites →https://doi.org/10.1016/s0020-7373(75)80002-2openalex-snapshot
An experiment in linguistic synthesis with a fuzzy logic controller
inferredcites →https://doi.org/10.1109/91.919250openalex-snapshot
Cascaded fuzzy neural network model based on syllogistic fuzzy reasoning
inferredcites →https://doi.org/10.1109/tns.2007.911136openalex-snapshot
Detection and Diagnostics of Loss of Coolant Accidents Using Support Vector Machines
inferredcites →https://doi.org/10.1109/tns.2014.2305444openalex-snapshot
Smart Sensing of the RPV Water Level in NPP Severe Accidents Using a GMDH Algorithm
inferredcites →https://doi.org/10.1109/tns.2015.2457446openalex-snapshot
Estimation of Minimum DNBR Using Cascaded Fuzzy Neural Networks
inferredcites →https://doi.org/10.1109/tsmc.1985.6313399openalex-snapshot
Fuzzy identification of systems and its applications to modeling and control
inferredcites →https://doi.org/10.13182/nse94-a28534openalex-snapshot
Fault Diagnosis Via Neural Networks: The Boltzmann Machine
inferredcites →https://doi.org/10.13182/nt88-a16054openalex-snapshot
Diagnostic Techniques of a Small-Break Loss-of-Coolant Accident at a Pressurized Water Reactor Plant
inferredcites →https://doi.org/10.13182/nt92-a34635openalex-snapshot
Nuclear Power Plant Status Diagnostics Using an Artificial Neural Network
inferredcites →https://doi.org/10.13182/nt95-a15850openalex-snapshot
Evaluation of Reflooding Effects on an Overheated Boiling Water Reactor Core in a Small Steam-Line Break Accident Using MAAP, MELCOR, and SCDAP/RELAP5 Computer Codes
inferredcites →https://doi.org/10.13182/nt97-a35385openalex-snapshot
Signal Validation Using an Adaptive Neural Fuzzy Inference System
inferredcites →https://doi.org/10.5516/net.04.2012.512openalex-snapshot
MONITORING SEVERE ACCIDENTS USING AI TECHNIQUES
inferredcites →https://doi.org/10.5516/net.04.2013.087openalex-snapshot
PREDICTION OF THE REACTOR VESSEL WATER LEVEL USING FUZZY NEURAL NETWORKS IN SEVERE ACCIDENT CIRCUMSTANCES OF NPPS
inferredcites →https://doi.org/10.5516/net.2007.39.2.133openalex-snapshot
VALIDATION OF ON-LINE MONITORING TECHNIQUES TO NUCLEAR PLANT DATA
inferredcites →https://doi.org/10.5516/net.2007.39.2.149openalex-snapshot
EVALUATION OF PROLIFERATION RESISTANCE USING THE INPRO METHODOLOGY
inferredcites →https://doi.org/10.5516/net.2008.40.1.069openalex-snapshot
A SOFT-SENSING MODEL FOR FEEDWATER FLOW RATE USING FUZZY SUPPORT VECTOR REGRESSION
What points at this work
Incoming claims: where this work appears in other papers’ reference lists and arguments.
inferred← citeshttps://doi.org/10.1016/j.anucene.2018.12.010openalex-snapshot
Implication of LOCA characteristics of large PWR and SMR for future development of intelligent nuclear power plant control system
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Critical flow prediction using simplified cascade fuzzy neural networks
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Prediction of the internal states of a nuclear power plant containment in LOCAs using rule-dropout deep fuzzy neural networks
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Application of Data-Driven technology in nuclear Engineering: Prediction, classification and design optimization
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Enhancing prediction accuracy for LOCA break sizes in nuclear power plants: A hybrid deep learning method with data augmentation and hyperparameter optimization
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Shaping the future of nuclear reactors with digital twins: Current developments and perspectives
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Loss of coolant accident monitoring and pipe break diagnosis in pressurized water reactors using Bayesian-optimized long short-term memory models
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Artificial intelligence in nuclear industry: Chimera or solution?
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Leak flow prediction during loss of coolant accidents using deep fuzzy neural networks
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The ensemble approach in comparison with the diverse feature selection techniques for estimating NPPs parameters using the different learning algorithms of the feed-forward neural network
inferred← citeshttps://doi.org/10.1016/j.net.2024.01.035openalex-snapshot
A machine learning informed prediction of severe accident progressions in nuclear power plants
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A Simulation and Machine Learning Informed Diagnosis of the Severe Accidents
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2023.112711openalex-snapshot
Prediction of LOCA’s break size and location based on random forest and Multi Tasking Deep Neural Network
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2023.112781openalex-snapshot
A machine learning diagnosis of the severe accident progression
inferred← citeshttps://doi.org/10.1016/j.pnucene.2018.07.004openalex-snapshot
A study on the robustness of neural network models for predicting the break size in LOCA
inferred← citeshttps://doi.org/10.1016/j.pnucene.2021.103902openalex-snapshot
Diagnosis of break size and location in LOCA and SGTR accidents using support vector machines
inferred← citeshttps://doi.org/10.1016/j.pnucene.2024.105568openalex-snapshot
pyMAISE: A Python platform for automatic machine learning and accelerated development for nuclear power applications
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Hydrogen risk analysis for severe accidents in nuclear power plants using LightGBM algorithm on different quantiles
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An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents
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Interpretable Time Series Data Prediction for Severe Nuclear Accidents
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A Deep Learning Method to Predict Loss of Coolant Accident in Nuclear Power Plants
inferred← citeshttps://doi.org/10.1109/tns.2017.2743098openalex-snapshot
Identification of LOCA and Estimation of Its Break Size by Multiconnected Support Vector Machines
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An Accident Diagnosis Method of CFETR Water-Cooled Blanket Based on Deep Neural Network
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Resilient Machine Learning: Advancement, Barriers, and Opportunities in the Nuclear Industry
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Enhancement of Reflood Test Prediction by Integrating Machine Learning and Data Assimilation Technique
inferred← citeshttps://doi.org/10.1515/kern-2025-0027openalex-snapshot
Prediction of LOCA break sizes using LSTM architecture for pressurized water reactors
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Development of a NO x emission model with seven optimized input parameters for a coal-fired boiler
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An Intelligent Technique for Prevention of Hydrogen Explosion in Nuclear Power Plants
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Development of a Machine Learning Method to Predict the Break Diameter during PWR Loss-of-Coolant Accident
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Enhancing LOCA Breach Size Diagnosis with Fundamental Deep Learning Models and Optimized Dataset Construction
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