Abstract
Life extensions of nuclear power plants (NPPs) to 60 years of operation and the possibility of subsequent license renewal to 80 years have renewed interest in long-term material degradation in NPPs. Large irreplaceable sections of most nuclear generating stations are constructed from concrete, including safety-related structures such as biological shields and containment buildings; therefore, concrete degradation is being considered with particular focus on radiation-induced effects. Based on the projected neutron fluence values (E > 0.1 MeV) in the concrete biological shields of the US pressurized water reactor fleet and the currently available data on radiation effects on concrete, some decrease in mechanical properties of concrete cannot be ruled out during extended operation beyond 60 years. An expansion of the irradiated concrete database is desirable to ensure reliable risk assessment for extended operation of nuclear power plants.
Highlights
Numerous nuclear power plants (NPPs) in the USA have received approval to extend their licenses to operate up to 60 years and further extensions, to 80 years and beyond, are being considered to meet future national energy needs while reducing greenhouse gas emissions
Large structures of NPPs are built from concrete, including safety-related structures such as the biological shields and containment buildings
A research program on concrete aging and degradation processes in NPPs was established within the Light Water Reactor Sustainability (LWRS) program under the US Department of Energy (DOE) and is being performed in partnership with the Electric Power Research Institute’s Long-Term Operations (LTO) Program
Summary
Numerous nuclear power plants (NPPs) in the USA have received approval to extend their licenses to operate up to 60 years and further extensions, to 80 years and beyond, are being considered to meet future national energy needs while reducing greenhouse gas emissions. A recent review of Hillsdorf’s data by Kontani et al.[2] (2013) revealed that most data points at high end of neutron fluence range were obtained at irradiation temperatures above 100°C and were using either aluminous cement or liquid glass aggregate, which is not representative of the environment and materials used in concrete for NPPs. it is not surprising that the recently completed Expanded. A research program on concrete aging and degradation processes in NPPs was established within the Light Water Reactor Sustainability (LWRS) program under the US Department of Energy (DOE) and is being performed in partnership with the Electric Power Research Institute’s Long-Term Operations (LTO) Program.
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