Siemens Aktiengesellschaft

Kraftwerk Union Aktiengesellschaft

Rainer Schilling

Hermann-Josef Conrads

Erwin Laurer

Pius Mackert

Werner Leidemann

Jurgen Model

Walter Merklein

Bernd Staehle

Michael Seiter

Wilfried Stoll

Horst Goggelmann

Paul Uyttendaele

Jurgen Czech

A steam power station, in particular a nuclear power station, includes a steam conduit leading through a wall and forming a fixed point with the wall for the introduction of forces and moments. A main valve is connected to the steam conduit at the fixed point, without a high-pressure pipe being interposed. Satellite valves, which have smaller nominal widths than the main valve, are fastened to the housing of the main valve, without a high-pressure pipe being interposed. At least one additional valve has a housing fastened to the housing of a satellite valve, without a high-pressure pipe being interposed and without any support.

Steam power station

A pressurized water reactor residual heat extraction system uses the secondary cooling circuit to extract the residual heat in certain operating and malfunction conditions. A steam generator (D1) has a connection, located on the live-steam and feed-water side, to the secondary circuit side of a safety condenser (SK1). The tertiary circuit side of the safety condenser is fed from a water reservoir (B) located at a physically higher level. The steam generated is vented to the atmosphere through a blow-off line (b2) which may include a separator. A make-up feed device (E1) is connected to the secondary side of the steam generator. Because of the higher location of the safety condenser with respect to the steam generator, the heat energy in the secondary cooling circuit circulates by natural circulation.

Secondary-side residual-heat removal system for pressurized-water

Emergency feed system for cooling nuclear reactor installations having a vessel for containing deionate which is fed to a steam generator through an emergency feed pump having a suction line connected to the vessel includes a circulating line extending at one end thereof from the vessel and having connected therein a circulating pump and heat exchanger means for cooling components of the emergency feed system, valve means connected to the other end of the circulating line, and a pair of lines both extending from the valve means and connected, respectively, to the suction line of the emergency feed pump and to a drainage system.

Emergency feed system for cooling nuclear reactor installations

Growing community of inventors

Erlangen, Germany

Rainer Schilling