FIELD: nuclear power installations of water-moderated water-cooled type.
SUBSTANCE: proposed system designed for evacuating steam-gas mixture from primary circuit to prevent formation of critical concentration of oxygen and hydrogen at separate points of primary circuit and to avoid failure of natural circulation therein has reactor with core and steam generator with vertical "cold" and "hot" headers connected by means of horizontal heat-transfer tube bundles, main circulating pumps, first pressurizer with steam cavity communicating with top parts of vertical headers and top part of main circulating pump with pipelines incorporating shutoff valves with hydraulic actuators. Hydraulic-actuator cylinder is divided into intake and discharge working cavities; intake cavity communicates with pressure end of main circulating pump and discharge one, with its suction end; throttles are installed on pipelines interconnecting vertical "hot" headers of steam generators and vertical "cold" ones, as well as on pipelines interconnecting vertical "hot" headers and top part of main circulating pump.
EFFECT: enhanced safety and efficiency.
1 cl, 2 dwg
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Authors
Dates
2006-04-10—Published
2004-08-20—Filed