Monitoring, Modeling, and Diagnosis of Alkali-Silica Reaction in Small Concrete Samples
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
Assessment and management of aging concrete structures in nuclear power plants require a more systematic approach than simple reliance on existing code margins of safety. Structural health monitoring of concrete structures aims to understand the current health condition of a structure based on heterogeneous measurements to produce high-confidence actionable information regarding structural integrity that supports operational and maintenance decisions. This report describes alkali-silica reaction (ASR) degradation mechanisms and factors influencing the ASR. A fully coupled thermo-hydro-mechanical-chemical model developed by Saouma and Perotti by taking into consideration the effects of stress on the reaction kinetics and anisotropic volumetric expansion is presented in this report. This model is implemented in the GRIZZLY code based on the Multiphysics Object Oriented Simulation Environment. The implemented model in the GRIZZLY code is randomly used to initiate ASR in a 2D and 3D lattice to study the percolation aspects of concrete. The percolation aspects help determine the transport properties of the material and therefore the durability and service life of concrete. This report summarizes the effort to develop small-size concrete samples with embedded glass to mimic ASR. The concrete samples were treated in water and sodium hydroxide solution at elevated temperature to study how ingress of sodium ions and hydroxide ions at elevated temperature impacts concrete samples embedded with glass. Thermal camera was used to monitor the changes in the concrete sample and results are summarized.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1245691
- Report Number(s):
- INL/EXT-15-36683; M2LW-15IN0602084; TRN: US1601245
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CONCRETES
SODIUM HYDROXIDES
SODIUM IONS
SILICA
NUCLEAR POWER PLANTS
SOLUTIONS
COMPUTERIZED SIMULATION
CHEMICAL REACTION KINETICS
GLASS
HARDNESS
WATER
ANISOTROPY
EXPANSION
DECOMPOSITION
RANDOMNESS
STRESSES
TEMPERATURE RANGE 0273-0400 K
TIME DEPENDENCE
Alkali Silica Reaction
Concrete Sample with Embedded Glass
Concrete Structural Health Monitoring
MOOSE Modeling
Percolation Theory