Degradation and Failure Characteristics of NPP Containment Protective Coating Systems Page: 3 of 124
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WSRC-TR-2000-00340
Abstract
A research program to investigate the performance and potential for failure of Service Level I coating systems used
in nuclear power plant containment is in progress. The research activities are aligned to address phenomena
important to cause failure as identified by the industry coatings expert panel. The period of interest for performance
covers the time from application of the coating through 40 years of service, followed by a medium-to-large break
loss-of-coolant accident scenario, which is a design basis accident (DBA) scenario.
The SRTC program consists of three major elements: Materials Properties Development, Failure Modeling
Development, and DBA Performance Testing. These elements are directed at determining Service Level I coatings
performance under simulated DBA conditions. The coating materials properties data (not previously available) are
used in predictive coatings failure models which are then compared against coating behavior under simulated DBA
conditions to obtain insights into failed coating materials characteristics and degree of failure (i.e. amount of
coatings debris). The resulting data and insights are used in NRC's GSI-191, "PWR Sump Blockage" research
program. The effects of aging on coating materials properties and performance are addressed by applying an aging
treatment (irradiation to 109 R, per ASTM D4082-95) to test specimens.
The interactive program elements are discussed in this report and the application of these elements to the SRTC
System 2 coating system (Phenoline 305 epoxy-phenolic topcoat, Starglaze* 2011S surfacer, concrete substrate) is
used to evaluate performance. The SRTC System 2 coating system represents one of the predominant coating
systems applied to concrete substrates in NPP containment. In order to evaluate the performance of coatings already
in place, SRTC obtained original formulations of Phenoline 305 for use in testing. Starglaze 2011S is
representative of concrete surfacer formulations which are in current use.
The Service Level designation of coatings in nuclear power plants is described in ASTM Standard D5144-00
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Sindelar, R.L. Degradation and Failure Characteristics of NPP Containment Protective Coating Systems, report, December 1, 2000; South Carolina. (https://digital.library.unt.edu/ark:/67531/metadc715389/m1/3/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.