Report on aging of nuclear power plant reinforced concrete structures

Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation

“…When taking into account the continuous use of NPPs over 40 years, the damage cause by these aging parameters on the components of NPPs can be substantially high. Out of all the components of a NPP, the items that are most vulnerable for radiation and thermal degradation are power cables and concrete components [2]. In this study, we are concentrating on degradation of insulation materials in low-voltage instrumentation and control cables in NPPs.…”

Overview of activities in the U.S. related to continued service of nuclear power plant concrete structures

“…Knowing where to inspect and what type of degradation to anticipate often requires information about the design features of the NPP structures as well as the materials of construction and environmental factors. A number of documents are available to assist in development and conduct of structural condition assessment programs and providing guidance addressing assessment of concrete degradation [3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18][19][20][21][22].…”

“…The digitized database will not only store data and information, but also register the relationships between data and information to enable accurate traceability to satisfy pedigree and prediction research needs. Since both the previously developed SMIC and the NCMD currently being developed use the same formatting structure as the Nuclear Systems Materials Handbook that was developed in the 1970's under the Liquid-Metal Fast-Breeder Reactor Program [52], initial data and information input into the NCMD will be provided by the Structural Materials Information Center that was developed under the USNRC Structural Aging Program [7].…”

Containment Liner Corrosion

“…Those plants employ a steel containment liner in contact with concrete. 1,4 In 1996 the NRC amended its regulations (10 CFR 50.55a) to incorporate by reference the 1992 Edition and Addenda of Subsections IWE and IWL of Section XI of the ASME code to assure that critical areas of the containments are routinely inspected to detect and to take corrective action for defects that could compromise the integrity of the containment structure. Specifically, NRC Information Notice 97-29 stated that the amended rule became effective on September 9, 1996.…”