Artificial neural network for predicting nuclear power plant dynamic behaviors
Искусственная нейронная сеть для прогнозирования динамического поведения атомной электростанции
2021-05-20
SCID: 54.1/h5emv2an
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artificial neural networkdata-driven modelsdynamic behavior predictionnuclear power plantpressurized water reactor
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Abstract (AI)
A Nuclear Power Plant (NPP) is a complex dynamic system-of-systems with highly nonlinear behaviors. In order to control the plant operation under both normal and abnormal conditions, the different systems in NPPs (e.g., the reactor core components, primary and secondary coolant systems) are usually monitored continuously, resulting in very large amounts of data. This situation makes it possible to integrate relevant qualitative and quantitative knowledge with artificial intelligence techniques to provide faster and more accurate behavior predictions, leading to more rapid decisions, based on actual NPP operation data. Data-driven models (DDM) rely on artificial intelligence to learn autonomously based on patterns in data, and they represent alternatives to physics-based models that typically require significant computational resources and might not fully represent the actual operation conditions of an NPP. In this study, a feed-forward backpropagation artificial neural network (ANN) model was trained to simulate the interaction between the reactor core and the primary and secondary coolant systems in a pressurized water reactor. The transients used for model training included perturbations in reactivity, steam valve coefficient, reactor core inlet temperature, and steam generator inlet temperature. Uncertainties of the plant physical parameters and operating conditions were also incorporated in these transients. Eight training functions were adopted during the training stage to develop the most efficient network. The developed ANN model predictions were subsequently tested successfully considering different new transients. Overall, through prompt prediction of NPP behavior under different transients, the study aims at demonstrating the potential of artificial intelligence to empower rapid emergency response planning and risk mitigation strategies.
Key Findings
1
A feed-forward backpropagation artificial neural network was developed to simulate interactions among the reactor core, primary coolant, and secondary coolant systems in a pressurized water reactor.
2
Eight training functions were evaluated to identify an efficient neural-network configuration.
3
The ANN was trained on transients involving reactivity, steam-valve coefficient, reactor-core inlet temperature, and steam-generator inlet temperature perturbations.
4
The developed ANN successfully predicted previously unseen transients, demonstrating potential for rapid NPP behavior prediction and emergency-response planning.
5
Uncertainties in physical plant parameters and operating conditions were incorporated into the training transients to improve model applicability to realistic operation.
Research Object
The reactor core and primary and secondary coolant systems of a pressurized water nuclear power plant
Research Subject
Their dynamic behavior and interactions under normal and abnormal transients, including prediction accuracy under parameter and operating-condition uncertainties
Publication Details
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2021-05-20
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