TY - JOUR
T1 - FFT-based model for irradiated aggregate microstructures in concrete
AU - Cheniour, Amani
AU - Li, Yujie
AU - Sanahuja, Julien
AU - Le Pape, Yann
AU - Tajuelo Rodriguez, Elena
AU - Anovitz, Lawrence M.
AU - Polavaram, Krishna C.
AU - Garg, Nishant
AU - Rosseel, Thomas M.
N1 - This work is supported by the US Department of Energy\u2019s (DOE\u2019s) Office of Nuclear Energy Light Water Reactor Sustainability Program under contract number DE-AC05-00OR22725 and Effects of Irradiation on Bond Strength in Concrete Structures project (31310018S0021) of the US Nuclear Regulatory Commission. The authors also acknowledge support from the US Department of Energy\u2019s Nuclear Energy University Program under contract number DE-NE0008886. The authors thank JCAMP and researchers Maruyama (Nagoya University), Takizawa (Mitsubishi Research Institute), and Kontani (Kajima Corporation) for sharing the unirradiated rock specimens that made this research possible. This cooperation is supported by the Civil Nuclear Energy Research and Development Working Group, a joint organization between DOE and the Japanese Agency for Natural Resources and Energy of the Ministry of Economy, Trade and Industry. This research is also supported by the Horizon 2020 European Commission Project ACES (\u201CImproved assessment of NPP concrete structures toward ageing\u201D). The authors thank Susan Ennaceur and Albert Migliori from Alamo Creek Engineering for providing preliminary estimates of the Young\u2019s modulus for some of the aggregates by using Resonance Ultrasound Spectroscopy.
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 ).
PY - 2022/10
Y1 - 2022/10
N2 - The concrete biological shield of light water reactors is exposed to neutron and gamma irradiation throughout its lifetime, which results in the long-term degradation of the concrete’s mechanical properties. Under neutron irradiation, the concrete’s aggregates are subjected to radiation-induced volumetric expansion (RIVE), which strongly depends on the mineral content of the aggregate and exhibits the largest expansion in silicate-bearing minerals. In this work, the authors used the fast Fourier transform-based code Microstructure-Oriented Scientific Analysis of Irradiated Concrete (MOSAIC) in 2D to model the expansion of five different aggregates provided by the Japan Concrete Aging Management Program (JCAMP). Comparable rock specimens were irradiated at the JEEP-II test reactor. The model uses realistic aggregate microstructure reconstruction based on high-resolution characterization images. The model accounts for anisotropic RIVE, thermal expansion, and the associated initiation and propagation of damage. The RIVE models are calibrated based on expansion data in the literature. The authors assume that damage occurs exclusively at interfaces between the particles that compose an aggregate and that these interfaces also exhibit swelling. Using a micromechanical model, the evolution of Young’s modulus with RIVE is calculated for each aggregate and compared with Russian irradiation data. The modeled linear expansion agrees well with the experimentally measured expansion. The model also predicts that anisotropic RIVE and thermal expansion result in an earlier onset of damage with neutron fluence than in the isotropic case.
AB - The concrete biological shield of light water reactors is exposed to neutron and gamma irradiation throughout its lifetime, which results in the long-term degradation of the concrete’s mechanical properties. Under neutron irradiation, the concrete’s aggregates are subjected to radiation-induced volumetric expansion (RIVE), which strongly depends on the mineral content of the aggregate and exhibits the largest expansion in silicate-bearing minerals. In this work, the authors used the fast Fourier transform-based code Microstructure-Oriented Scientific Analysis of Irradiated Concrete (MOSAIC) in 2D to model the expansion of five different aggregates provided by the Japan Concrete Aging Management Program (JCAMP). Comparable rock specimens were irradiated at the JEEP-II test reactor. The model uses realistic aggregate microstructure reconstruction based on high-resolution characterization images. The model accounts for anisotropic RIVE, thermal expansion, and the associated initiation and propagation of damage. The RIVE models are calibrated based on expansion data in the literature. The authors assume that damage occurs exclusively at interfaces between the particles that compose an aggregate and that these interfaces also exhibit swelling. Using a micromechanical model, the evolution of Young’s modulus with RIVE is calculated for each aggregate and compared with Russian irradiation data. The modeled linear expansion agrees well with the experimentally measured expansion. The model also predicts that anisotropic RIVE and thermal expansion result in an earlier onset of damage with neutron fluence than in the isotropic case.
KW - Fast Fourier transform
KW - Irradiated concrete
KW - MOSAIC
KW - Micromechanics
UR - http://www.scopus.com/inward/record.url?scp=85139389510&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85139389510&partnerID=8YFLogxK
U2 - 10.1617/s11527-022-02010-x
DO - 10.1617/s11527-022-02010-x
M3 - Article
AN - SCOPUS:85139389510
SN - 1359-5997
VL - 55
JO - Materials and Structures/Materiaux et Constructions
JF - Materials and Structures/Materiaux et Constructions
IS - 8
M1 - 214
ER -