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

US5428652A · kind A · utility

Assignee

• Siemens Aktiengesellschaft · DE

Inventors

• Hermann-Josef Conrads · Herzogenaurach, DE
• Jurgen Czech · Herzogenaurach, DE
• Horst Goggelmann · Fürth, DE
• Werner Leidemann · Herzogenaurach, DE
• Pius Mackert · Erlangen, DE
• Walter Merklein · Nürnberg, DE
• Rainer Schilling
• Bernd Staehle · Erlangen, DE
• Wilfried Stoll · Nürnberg, DE
• Paul Uyttendaele · Erlangen, DE

Key dates

• Filing date: Feb 14, 1994
• Grant date: Jun 27, 1995
• Expiry date: Feb 14, 2014

Classification

• Technology area (CPC Y): Emerging Cross-Sectional Technologies
• CPC primary: Y02E30/30
• WIPO field: Engines, pumps, turbines
• WIPO sector: Mechanical engineering

Abstract

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.