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.

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