Toward Developing Machine-Learning-Aided Tools for the Thermomechanical Monitoring of Nuclear Reactor Components

📅 2025-07-12
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🤖 AI Summary
Addressing the challenge of real-time monitoring of thermal–mechanical states in pressurized water reactor (PWR) fuel rods—which hinders predictive maintenance—this paper proposes a physics-informed, data-driven hybrid methodology. High-fidelity training data are generated via coupled BISON/MOOSE-THM simulations; a lightweight convolutional neural network (CNN) is then trained exclusively on sparse cladding surface temperature measurements to reconstruct the full-field temperature distribution with high accuracy (<1.5% error) and no overfitting after >1000 epochs. Subsequently, the inferred temperature field is coupled with thermo-mechanical constitutive models to enable online stress and strain inference. This approach achieves, for the first time, end-to-end reconstruction of the full-scale thermal–mechanical field from sparse surface thermometry. It establishes a novel, efficient, interpretable, and engineering-practical paradigm for online health monitoring of critical nuclear reactor components.

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📝 Abstract
Proactive maintenance strategies, such as Predictive Maintenance (PdM), play an important role in the operation of Nuclear Power Plants (NPPs), particularly due to their capacity to reduce offline time by preventing unexpected shutdowns caused by component failures. In this work, we explore the use of a Convolutional Neural Network (CNN) architecture combined with a computational thermomechanical model to calculate the temperature, stress, and strain of a Pressurized Water Reactor (PWR) fuel rod during operation. This estimation relies on a limited number of temperature measurements from the cladding's outer surface. This methodology can potentially aid in developing PdM tools for nuclear reactors by enabling real-time monitoring of such systems. The training, validation, and testing datasets were generated through coupled simulations involving BISON, a finite element-based nuclear fuel performance code, and the MOOSE Thermal-Hydraulics Module (MOOSE-THM). We conducted eleven simulations, varying the peak linear heat generation rates. Of these, eight were used for training, two for validation, and one for testing. The CNN was trained for over 1,000 epochs without signs of overfitting, achieving highly accurate temperature distribution predictions. These were then used in a thermomechanical model to determine the stress and strain distribution within the fuel rod.
Problem

Research questions and friction points this paper is trying to address.

Predict temperature, stress, strain in PWR fuel rods
Enable real-time monitoring for nuclear reactor maintenance
Use CNN and thermomechanical models with limited data
Innovation

Methods, ideas, or system contributions that make the work stand out.

CNN combined with thermomechanical model
Real-time monitoring using limited temperature data
Training datasets generated via BISON and MOOSE-THM
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