American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 212 / Number 9

Uncertainty Quantification for Neutron Shield Using Convolutional Neural Networks

J. C. Zamora, G. Bollen, T. Ginter, R. Pal Chowdhury

Nuclear Technology / Volume 212 / Number 9 / September 2026 / Pages 2431-2438

Research Article / dx.doi.org/10.1080/00295450.2025.2521881

Received:January 29, 2025
Accepted:June 10, 2025
Published:July 27, 2026

Uncertainty quantification from radiation transport calculations was conducted using a Bayesian inference approach. A surrogate model, using a convolutional neural network, was employed to emulate the neutron fluence, which was simulated with a Monte Carlo radiation transport model. This allowed for a computationally cheap approach to evaluate input parameters and to sample their corresponding posterior probability distributions. Experimental data from the literature were employed to perform uncertainty quantification studies for concrete shields. The method is a nonintrusive approach that enables studies with multiple input parameters and can be applied to any radiation transport model.