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Comparison of various DNN modelling strategies for assembly node averaged multigroup cross section representation for nodal codes
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.ORCID iD: 0000-0002-7943-7517
2024 (English)In: Proceedings of the International Conference on Physics of Reactors, PHYSOR 2024, American Nuclear Society , 2024, p. 1664-1673Conference paper, Published paper (Refereed)
Abstract [en]

A deep neural network model is proposed to predict assembly node cross section libraries based on fuel pellet nuclide concentrations and instantaneous state parameters.We tested the impact of two different factors on model p erformance.The first factor is the impact of averaging fuel pellet nuclide compositions and the second factor is the use of a single large DNN model versus the use of multiple DNNs for different cross section p arameters.The combination of the two factors result in four variations of the model architecture.All four architectures are rigourously tested and statistically compared using the Nemenyi posthoc test.The pair-wise Nemenyi results indicates that the averaging of fuel pellet nuclide concentrations had no impact on model performance.However, the results show a clear improvement of the representational model when a single large DNN model is used compared with multiple smaller DNN models.The selected best model with averaged fuel pellet compositions and a single large DNN model was tested on previously unseen data.The model was shown to have high accuracy with less than 1% mean relative error for the fission and total cross section values.

Place, publisher, year, edition, pages
American Nuclear Society , 2024. p. 1664-1673
Keywords [en]
DNN, Nemenyi posthoc, Nodal cross section library
National Category
Electrical Engineering, Electronic Engineering, Information Engineering
Identifiers
URN: urn:nbn:se:kth:diva-353523DOI: 10.13182/PHYSOR24-43304Scopus ID: 2-s2.0-85202808045OAI: oai:DiVA.org:kth-353523DiVA, id: diva2:1899198
Conference
2024 International Conference on Physics of Reactors, PHYSOR 2024, San Francisco, United States of America, Apr 21 2024 - Apr 24 2024
Note

QC 20240927

 Part of ISBN 9780894487972

Available from: 2024-09-19 Created: 2024-09-19 Last updated: 2025-09-25Bibliographically approved
In thesis
1. Machine learning methods in reactor lattice and nodal calculations
Open this publication in new window or tab >>Machine learning methods in reactor lattice and nodal calculations
2025 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

 This thesis investigates the application of advanced machine learning (ML) techniques for reactor physics applications, specifically in the area of lattice and nodal calculations. The research is divided into two main areas. The first focuses on accelerating the generation of few-group cross section (FGXS) data and the second area focuses on the use of ML for accurate predictions of nodal parameters and their uncertainty estimates.   In the first area, ML-based surrogate models were developed to predict multi-group cross section (MGXS) libraries for nuclides commonly found in pressurized water reactors (PWRs), serving as efficient alternatives to conventional tools such as XSPROC. Additionally, a hybrid model incorporating two deep neural networks (DNNs) with a linear blending scheme was proposed to simulate the depletion-driven evolution of nuclide compositions within fuel pellets. To manage the high dimensionality of MGXS data, Principal Component Analysis (PCA) was employed to construct a reduced latent space, which was then mapped using DNNs conditioned on reactor state parameters. Recurrent neural networks (RNNs) were also evaluated for modeling fuel depletion behavior. Two RNN variants—the “Direct NN” and the “Difference NN”—were developed and compared, and a nuclide-specific blending parameter optimized during training was introduced to enhance predictive performance without requiring additional training data.  The second area examines ML-based approaches for nodal data representation. Statistically rigorous model comparisons were performed using the non-parametric Wilcoxon, Nemenyi, McDonald-Thompson (WNMT) test. The study demonstrated that ML models can predict not only mean FGXS parameters but also their associated covariance matrices, capturing aleatoric uncertainty and enabling their integration into full-core uncertainty quantification frameworks. Both polynomial regression and DNN-based models were assessed, alongside the effects of descriptive statistical preprocessing. Results showed a strong dependence of model accuracy on training dataset size, with polynomial regression combined with descriptive statistics yielding the most accurate predictions on the largest dataset.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2025. p. ix, 68
Series
TRITA-SCI-FOU ; 2025:38
National Category
Other Engineering and Technologies
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-370472 (URN)978-91-8106-377-6 (ISBN)
Public defence
2025-09-26, FB51, Roslagstullsbacken 21, AlbaNova, Stockholm, 14:00 (English)
Supervisors
Note

QC 2025-09-25

Available from: 2025-09-25 Created: 2025-09-25 Last updated: 2025-10-27Bibliographically approved

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Chan, Yi MengDufek, Jan

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Citation style
  • apa
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  • Other style
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