A mesoscale 3D model of irradiated concrete informed via a 2.5 U-Net semantic segmentation

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Abstract

The concrete biological shield in light-water reactors is exposed to neutron and gamma irradiation, which deteriorates the concrete's mechanical properties in the long term. To assess the irradiation-induced damage, predictive mechanical models are developed and used in parallel with the characterization of irradiated concrete samples. Realistic 3D simulation domains can drastically improve a model's prediction. In this work, we utilized x-ray computed tomography (XCT) data of a concrete specimen to reconstruct its 3D microstructure. The XCT data shows low contrast between the concrete's aggregates and cement paste, resulting in poor image segmentation when using traditional unsupervised techniques. To address this issue, we developed and trained a 2.5D U-Net model on only 24 pre-labeled XCT layers to segment 651 layers of the XCT data. The overall F1-score of the model is approximately 96%. Then, we created a 3D finite element (FE) mesh based on the stack of segmented images. The FE model contains radiation-induced expansion, damage, and creep. The constitutive equations are adapted to each phase (aggregates and cement paste). We simulated the effects of neutron irradiation in the concrete specimen as well as the specimen's mechanical response to uniaxial compression. Finally, model validation was performed using experimental data on similar concrete specimens in the literature.

Original languageEnglish
Article number134392
JournalConstruction and Building Materials
Volume412
DOIs
StatePublished - Jan 19 2024

Funding

Notice: This manuscript has been authored by UT-Battelle LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This work is supported by the US Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability (LWRS) program under contract number DE-AC05-00OR22725 and by the Artificial Intelligence (AI) Initiative as part of the Laboratory Directed Research & Development (LDRD) Program at Oak Ridge National Lab (ORNL). This research made use of Idaho National Laboratory (INL) computing resources which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517. The authors thank Ercan Cakmak (ORNL) and J. David Arregui Mena (ORNL) for providing x-ray computed tomography (XCT) data of concrete specimens. The authors thank Thomas M. Rosseel (ORNL) for the insightful discussions. This work is supported by the US Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability (LWRS) program under contract number DE-AC05-00OR22725 and by the Artificial Intelligence (AI) Initiative as part of the Laboratory Directed Research & Development (LDRD) Program at Oak Ridge National Lab (ORNL) . This research made use of Idaho National Laboratory (INL) computing resources which are supported by the Office of Nuclear Energy of the US Department of Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517 . The authors thank Ercan Cakmak (ORNL) and J. David Arregui Mena (ORNL) for providing x-ray computed tomography (XCT) data of concrete specimens. The authors thank Thomas M. Rosseel (ORNL) for the insightful discussions.

FundersFunder number
Artificial Intelligence
Ercan Cakmak
LWRS
Office of Nuclear Energy, Light Water Reactor Sustainability
U.S. Department of Energy
Office of Nuclear EnergyDE-AC07-05ID14517
Oak Ridge National Laboratory
Laboratory Directed Research and Development
UT-BattelleDE-AC05-00OR22725

    Keywords

    • 2.5D U-Net
    • Image segmentation
    • Irradiated concrete
    • X-ray CT

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