PROTECTIVE SYSTEM OF PROTECTIVE SHELL OF WATER-COOLED REACTOR PLANT
designing and construction of nuclear power plants with water-cooled power reactors. SUBSTANCE: installed on the floor of the concentrate pit is a water-cooled insurance vessel with stiffening ribs providing for a guaranteed clearance between the insurance vessel and the inner surfaces of the concre...
Gespeichert in:
Hauptverfasser: | , , , , , , , , , , , , |
---|---|
Format: | Patent |
Sprache: | eng |
Schlagworte: | |
Online-Zugang: | Volltext bestellen |
Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
Zusammenfassung: | designing and construction of nuclear power plants with water-cooled power reactors. SUBSTANCE: installed on the floor of the concentrate pit is a water-cooled insurance vessel with stiffening ribs providing for a guaranteed clearance between the insurance vessel and the inner surfaces of the concrete pit. Cooling water is supplied to the clearance through the device passages for feeding of the heat-transfer agent, and the steam-water mixture comes out through the above passages for discharge of the heat-transfer agent. Refractory members are installed on the insurance vessel and feel the free space of the room of the concrete pit positioned under the reactor. Passive replenishment of the concrete pit with water is accomplished through the device passages for feeding of the heat-transfer agent, which provides for cooling of the external surface of the insurance vessel at a heating of its internal surface by corium supplied to the concrete pit room under the reactor. Protection of the insurance vessel against superallowed mechanical loads on the side of the destructed reactor equipment and corium is ensured by the concrete bracket, refractory members and protective shields. Protection against heat shocks is provided by refractory members, protective shields and heat- insulating layers. Enhanced reliability of heat removal is ensured by the two-layer insurance vessel, the space between the layers of which is filled with a fusible material providing for reduction of heat flow to water due to increased surface of intensive heat exchange. EFFECT: enhanced safety of nuclear power plant in case of destruction of the active zone and outflow of corium beyond the reactor vessel. 31 cl, 14 dwg |
---|