Prediction of the evolution of the nuclear reactor core parameters using artificial neural network
Krzysztof Palmi, Wojciech Kubinski, Piotr Darnowski

TL;DR
This paper develops an artificial neural network model to predict nuclear reactor core parameters, including fuel cycle length, using data from a PWR reactor simulation, aiming to enhance design efficiency and accuracy.
Contribution
The study introduces an optimized ANN architecture for reactor core parameter prediction, demonstrating high accuracy and potential to reduce simulation efforts in nuclear reactor design.
Findings
ANN predicted fuel cycle length with over 99% accuracy
Optimal ANN architecture outperformed existing models
Predictions varied with different core loading patterns
Abstract
A nuclear reactor based on MIT BEAVRS benchmark was used as a typical power generating Pressurized Water Reactor (PWR). The PARCS v3.2 nodal-diffusion core simulator was used as a full-core reactor physics solver to emulate the operation of a reactor and to generate training, and validation data for the ANN. The ANN was implemented with dedicated Python 3.8 code with Google's TensorFlow 2.0 library. The effort was based to a large extent on the process of appropriate automatic transformation of data generated by PARCS simulator, which was later used in the process of the ANN development. Various methods that allow obtaining better accuracy of the ANN predicted results were studied, such as trying different ANN architectures to find the optimal number of neurons in the hidden layers of the network. Results were later compared with the architectures proposed in the literature. For the…
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Taxonomy
TopicsNuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics · Nuclear Materials and Properties
