Abstract
Reactor cavity concrete, a major component of Light Water Reactors (LWRs), serves as a biological shield and as a structural support. The most important aging mechanisms that affect the structural integrity of reactor cavity concrete are neutron irradiation, alkali-silica reaction (ASR), and loss of moisture. All these phenomena reduce the strength and can generate cracks in the cavity concrete structures. Neutron irradiation can lead to the gradual amorphization of the minerals that form the aggregates. With time the amorphization of minerals induces the expansion of mineral phase resulting in radiation-induced volumetric expansion (RIVE) [1]. In a similar fashion, ASR induces swelling in the concrete. In this manuscript, the authors will present results from a series of complimentary microscopy techniques that can be used to characterize the RIVE and ASR effects to develop a more coherent understanding of how these effects degrade the integrity of the concrete. These techniques include x-ray computed tomography (XCT), transmission electron microscopy (TEM), x-ray fluorescence (XRF) and electron backscatter diffraction (EBSD). Using these techniques in combination is necessary to develop an understanding of the fundamental mechanisms that lead to concrete degradation.
Original language | English |
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Pages | 914-916 |
Number of pages | 3 |
State | Published - 2019 |
Externally published | Yes |
Event | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States Duration: Aug 18 2019 → Aug 22 2019 |
Conference
Conference | 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 |
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Country/Territory | United States |
City | Boston |
Period | 08/18/19 → 08/22/19 |
Funding
Oak Ridge National Laboratory is managed by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 for the U.S. Department of Energy. This research was supported by the U. S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability (LWRS) Program under contract DE-AC05-00OR22725 with UT-Battelle, LLC 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) Oak Ridge National Laboratory is managed by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 for the U.S. Department of Energy. This research was supported by the U. S. Department of Energy, Office of Nuclear Energy, Light Water Reactor Sustainability (LWRS) Program under contract DE-AC05-00OR22725 with UT-Battelle, LLC 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)