Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants Page: 3 of 58
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ABSTRACT
When performing seismic safety assessments of nuclear power plants (NPPs), the potential
effects of age-related degradation on structures, systems, and components (SSCs) should be
considered. To address the issue of aging degradation, the Korea Atomic Energy Research
Institute (KAERI) has embarked on a five-year research project to develop a realistic seismic risk
evaluation system which will include the consideration of aging of structures and components in
NPPs. Three specific areas that are included in the KAERI research project, related to seismic
probabilistic risk assessment (PRA), are probabilistic seismic hazard analysis, seismic fragility
analysis including the effects of aging, and a plant seismic risk analysis.
To support the development of seismic capability evaluation technology for degraded structures
and components, KAERI entered into a collaboration agreement with Brookhaven National
Laboratory (BNL) in 2007. The collaborative research effort is intended to continue over a five
year period with the goal of developing seismic fragility analysis methods that consider the
potential effects of age-related degradation of SSCs, and using these results as input to seismic
PRAs. In the Year 1 scope of work BNL collected and reviewed degradation occurrences in US
NPPs and identified important aging characteristics needed for the seismic capability evaluations
that will be performed in the subsequent evaluations in the years that follow. This information is
presented in the Annual Report for the Year 1 Task, identified as BNL Report-81741-2008 and
also designated as KAERI/RR-2931/2008. The report presents results of the statistical and
trending analysis of this data and compares the results to prior aging studies. In addition, the
report provides a description of U.S. current regulatory requirements, regulatory guidance
documents, generic communications, industry standards and guidance, and past research related
to aging degradation of SSCs.
This report describes the research effort performed by BNL for the Year 2 scope of work. This
research focused on methods that could be used to represent the long-term behavior of materials
used at NPPs. To achieve this BNL reviewed time-dependent models which can approximate the
degradation effects of the key materials used in the construction of structures and passive
components determined to be of interest in the Year 1 effort. The intent was to review the
degradation models that would cover the most common time-dependent changes in material
properties for concrete and steel components.iii
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Nie,J.; Braverman, J.; Hofmayer, C.; Kim, M. K. & Choi, I-K. Identification and Assessment of Material Models for Age-Related Degradation of Structures and Passive Components in Nuclear Power Plants, report, April 27, 2009; United States. (https://digital.library.unt.edu/ark:/67531/metadc932798/m1/3/: accessed April 23, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.