Nuclear power provides a heat source for steam-electric generation that does not pollute the atmosphere. Heat is produced in a nuclear reactor by the neutron radiation emitted by the steady-state fusion of enriched or natural uranium. The nuclear renaissance that is emerging in the United States will be based on new power plant designs from a variety of U.S. and international sources. The emerging designs have been designated as “Generation III” reactors. The most significant feature of Generation III reactor designs is that many incorporate passive or intrinsic safety features that, in the event of a malfunction or design-basis accident (DBA), require no operator intervention or active controls to mitigate the effects of the malfunction or DBA and avoiding core damage for an extended period of time. The Westinghouse AP1000® Pressurize Water Reactor (PWR) represents a progressive improvement of the original PWR. This paper will investigate the following: (1) differences between operating PWRs and the Westinghouse AP1000 Design, (2) primary regulations governing U.S. Nuclear Power Plants in relation to coatings, and (3) how the AP1000 design differences are translated into coatings system requirements.
How Design Features Unique to AP1000 Nuclear Power Plants Affect Coating System Design Requirements
Michael Durbin
Business Development Manager– Energy, Sherwin Williams Company NACE Level 3 Certified Coatings Inspector #8077 with Nuclear Facilities Certification
ASTM D33, E44
ASME member
ICRI Member
NACE Member
SSPC Member
IEEE Member
Experience
The Sherwin Williams Company - 1987 to Present– Protective and Marine Division, Global Finishes Group – Subject matter expertise includes coating system performance and selection, coating inspection standards, and application. Experienced in most aspects of protective coatings application with special experience in power generation, power transmission and bridge environments.
Patrick Ward
Patrick Ward is with Shaw as the Containment Liner Specialist and responsible engineer for the AP1000 coatings. He is a mechanical engineer in the civil structural department and has 38 years experience in the nuclear industry, including hydro and fossil.
Kristin Ruth
Kristin Ruth, Senior Engineer
B.S. Chemical Engineering, Pennsylvania State University (5/2008)
M.S. Mechanical Engineering, University of Pittsburgh (12/2011)
Post-Bachelor Certificate - Nuclear Engineering, University of Pittsburgh (12/2011)
4 years of AP1000® protective coatings experience at Westinghouse Electric Co.
Current author/owner of the Westinghouse Protective Coatings Specification for the Containment Vessel of the AP1000 Reactor Plant
Performed evaluations of post-design basis accident (DBA) chemical effects for Pressurized Water Reactors (PWR)
Performed wear and abrasion evaluations of PWR Emergency Core Cooling System (ECCS) equipment under post-DBA accident conditions
Hydraulic testing of a model fuel assembly under post-DBA accident conditions
Michael C. Durbin, Patrick Ward, Kristin Ruth; January 14–17, 2013. "How Design Features Unique to AP1000 Nuclear Power Plants Affect Coating System Design Requirements." Proceedings of the SSPC 2013 Greencoat. SSPC 2013 Greencoat. San Antonio, TX. (pp. 1-19). AMPP. https://doi.org/10.5006/S2013-00017
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