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Representation of multi-group cross section libraries and flux spectra for PWR materials with deep neural networks for lattice calculations
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering.
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering. AlbaNova Univ Ctr, KTH Royal Inst Technol, Div Nucl Engn, S-10691 Stockholm, Sweden..ORCID iD: 0000-0002-7943-7517
2024 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 208, article id 110746Article in journal (Refereed) Published
Abstract [en]

To compute few-group nodal data, lattice codes first need to generate multi-group cross-sections for each constituent material within the lattice model. This generation process utilizes continuous-energy cross-section libraries, which is expensive in terms of the computing cost. Moreover, any alteration in the nuclide compositions or other state parameters necessitates the repetition of this process. To reduce the computational demands, we propose the application of a pre-trained representational model. This model, which integrates Deep Neural Networks (DNN) and Principal Component Analysis (PCA) modules, is particularly beneficial in scenarios that require repeated multi-group data processing by the lattice code. In our previous research, we established that such a model could accurately generate multi-group data for fuel pellet materials. In the present study, we have broadened the scope of the model to encompass a more extensive range of materials typically found in pressurized water reactors, including zirc-alloy cladding and borated water moderators. We also show that the model can be trained on a wide spectrum of fuel enrichments. When integrated into lattice calculations, the errors introduced by the deep-learning-based representational model result in less than 1% deviation in the k eff and pin-power distribution. We have further refined the model to assess also the neutron fluxes in the fuel pellet and borated water. This refined model was subsequently employed to perform a flux-weighted collapse and generate few-group cross-section libraries for lattice calculation. The few-group libraries generated in this manner exhibited high accuracy and gave a low average k eff error and minimal errors in pin power distribution.

Place, publisher, year, edition, pages
Elsevier BV , 2024. Vol. 208, article id 110746
Keywords [en]
Cross section representation, Principal component analysis, Neural network, Deep learning, Lattice codes
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-351417DOI: 10.1016/j.anucene.2024.110746ISI: 001274336000001Scopus ID: 2-s2.0-85198951292OAI: oai:DiVA.org:kth-351417DiVA, id: diva2:1888322
Note

QC 20240812

Available from: 2024-08-12 Created: 2024-08-12 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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