4.7 Article

Damage development in neutron-irradiated concrete in a test reactor: Hygro-thermal and mechanical simulations

期刊

CEMENT AND CONCRETE RESEARCH
卷 142, 期 -, 页码 -

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.cemconres.2020.106349

关键词

Neutron irradiation; Finite element simulation; Radiation induced volumetric expansion; Damage; Elastic modulus

资金

  1. Department of Energy's Nuclear Energy University Program [DOE-NEUP: DE-NE0008398]
  2. U.S. Department of Energy [DE-AC05-00OR22725, DE-AC07-05ID14517]

向作者/读者索取更多资源

This study presents a 3D mesoscale simulation approach that considers the effects of temperature, moisture content, and high neutron fluence on damage prediction in concrete irradiated in a test reactor. The simulation framework involves hygro-thermal analysis and radiation-induced volumetric expansion, providing a predictive tool for quantifying damage in concrete due to neutron irradiation under different conditions.
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.

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