STEAM GENERATOR, PARTICULARLY FOR A PRESSURIZED-WATER NUCLEAR REACTOR

摘要

Steam generator, particularly for a pressurized water nuclear reactor, which has in per se known manner a water box in which circulates the hot water from the reactor core, and then enters a series of heat exchange tubes installed in a tube plate and extending within a secondary ferrule traversed by the secondary water, wherein the water box, secondary ferrule and tube plate are three independent, disassemblable assemblies.