TY - JOUR
T1 - Damage development in neutron-irradiated concrete in a test reactor
T2 - Hygro-thermal and mechanical simulations
AU - Saklani, Naman
AU - Banwat, Gaurav
AU - Spencer, Benjamin
AU - Rajan, Subramaniam
AU - Sant, Gaurav
AU - Neithalath, Narayanan
N1 - Funding Information:
NS, GB, SR, GS, and NN sincerely acknowledge the financial support for this research from the Department of Energy 's Nuclear Energy University Program (DOE-NEUP: DE-NE0008398 ). This manuscript has been co-authored by UT-Battelle, LLC (DE-AC05-00OR22725) (AG) and Battelle Energy Alliance, LLC (DE-AC07-05ID14517) (BS) under contract with the U.S. Department of Energy. The contents of this paper reflect the views and opinions of the authors, who are responsible for the accuracy of data presented, and do not necessarily reflect the views and policies of the funding agency, nor do the contents constitute a standard, specification, or regulation. The U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The authors also thank the anonymous reviewers, whose comments helped refine the manuscript significantly.
Funding Information:
NS, GB, SR, GS, and NN sincerely acknowledge the financial support for this research from the Department of Energy's Nuclear Energy University Program (DOE-NEUP: DE-NE0008398). This manuscript has been co-authored by UT-Battelle, LLC (DE-AC05-00OR22725) (AG) and Battelle Energy Alliance, LLC (DE-AC07-05ID14517) (BS) under contract with the U.S. Department of Energy. The contents of this paper reflect the views and opinions of the authors, who are responsible for the accuracy of data presented, and do not necessarily reflect the views and policies of the funding agency, nor do the contents constitute a standard, specification, or regulation. The U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The authors also thank the anonymous reviewers, whose comments helped refine the manuscript significantly.
Publisher Copyright:
© 2021 Elsevier Ltd
PY - 2021/4
Y1 - 2021/4
N2 - This paper reports the development of a 3D mesoscale hygro-thermal-mechanical simulation approach to predict damage in concrete irradiated in a test reactor. This framework, developed in MOOSE, considers the effects of elevated temperature, moisture content, and high neutron fluence (energy threshold, E > 0.1 MeV) on the mortar and aggregates separately. The first-stage simulation implements hygro-thermal analysis to determine the temperature and RH inside the specimen as a function of imposed radiation energy. These are used as inputs to the second stage, which considers radiation-induced volumetric expansion (RIVE) of aggregates, and creep, shrinkage, and stress-strain response of mortar to predict the expansion, stresses, and damage in specimens made using different coarse aggregates and subjected to different irradiation times. The irradiation time-dependent damage in the mortar is expressed using an isotropic damage parameter. This multi-physics model serves as a predictive tool for damage quantification in concrete due to neutron irradiation.
AB - This paper reports the development of a 3D mesoscale hygro-thermal-mechanical simulation approach to predict damage in concrete irradiated in a test reactor. This framework, developed in MOOSE, considers the effects of elevated temperature, moisture content, and high neutron fluence (energy threshold, E > 0.1 MeV) on the mortar and aggregates separately. The first-stage simulation implements hygro-thermal analysis to determine the temperature and RH inside the specimen as a function of imposed radiation energy. These are used as inputs to the second stage, which considers radiation-induced volumetric expansion (RIVE) of aggregates, and creep, shrinkage, and stress-strain response of mortar to predict the expansion, stresses, and damage in specimens made using different coarse aggregates and subjected to different irradiation times. The irradiation time-dependent damage in the mortar is expressed using an isotropic damage parameter. This multi-physics model serves as a predictive tool for damage quantification in concrete due to neutron irradiation.
KW - Damage
KW - Elastic modulus
KW - Finite element simulation
KW - Neutron irradiation
KW - Radiation induced volumetric expansion
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U2 - 10.1016/j.cemconres.2020.106349
DO - 10.1016/j.cemconres.2020.106349
M3 - Article
AN - SCOPUS:85099266038
SN - 0008-8846
VL - 142
JO - Cement and Concrete Research
JF - Cement and Concrete Research
M1 - 106349
ER -