Siemens Aktiengesellschaft

Gerhard Hau

Lothar Wistuba

Josef Hollmann

Hartmut Seidelberger

Dietmar Bittermann

Horst Weisshaupl

Horst-Dieter Stockhausen

Peter Rau

Manfred Fischer

Werner Meier

Anton Kautetzky

Andreas Gobel

Jorg Tschemernjak

Rainer Huber

Helmut Moldaschl

A retaining device has a multi-layer protective cladding for protecting the bearing and containment structure of a spreading chamber for the controlled spread and cooling of a melt from a nuclear reactor pressure vessel. The spreading chamber is configured under the spreading concept, i.e. the melt spreads and cools therein. The protective cladding has at least two layers: an outer sacrificial layer acts as a thermal shock barrier and melting substance; a protective and insulating layer, disposed inside the sacrificial layer and protecting the underlying bearing and containment structure, acts as thermal protection layer and retaining layer for the hot melt. The protective and insulating layer includes a first partial layer of fireproof concrete adjacent the bearing and containment structure, and a second partial layer of temperature-resistant ceramic blocks, in particular ZrO,adjacent the sacrificial layer.

Device for retaining a hot melt in particular a core melt-through inside the spreading chamber of a nuclear reactor installation

A nuclear reactor includes a propagation space for core melt. The propagation space has a coolant conduit leading to a coolant reservoir and a device which opens in a temperature-dependent manner. The coolant conduit in the propagation space is a spray conduit having a spraying area which covers the cross-section of the propagation space over a large area. The device is controlled in such a way that it opens when the core melt enters the propagation space. Spraying gives rise to a crust on the core melt which reduces heat radiation. At the same time, the propagation space fills with a steam atmosphere which drastically reduces the thermal load on building structures.

Nuclear reactor with a core melt propagation space provided with a

A device for collecting and cooling reactor-meltdown products from a reactor pressure vessel includes an antechamber disposed below the reactor pressure vessel and an expansion chamber for the reactor-meltdown products. A channel which is disposed between the antechamber and the expansion chamber has a partition being destructible by the reactor-meltdown products. A closure element which connects a coolant reservoir to the expansion chamber is destructible by the reactor-meltdown products. A method for collecting and cooling reactor-meltdown products from a reactor pressure vessel includes collecting reactor-meltdown products in an antechamber disposed below the reactor pressure vessel and keeping them in the antechamber for a predetermined time interval. A partition disposed between the antechamber and an expansion chamber is destroyed with the reactor-meltdown products. The reactor-meltdown products penetrate from the antechamber into the expansion chamber and are spread in the expansion chamber. A closure element is destroyed with the reactor-meltdown products in the expansion chamber, for connecting a coolant reservoir to the expansion chamber and permitting coolant to flow into the expansion chamber where it cools the reactor-meltdown products.

Device and method for collecting and cooling reactor-meltdown products

A device for collecting reactor-meltdown products from a reactor pressure vessel includes an antechamber disposed below the reactor pressure vessel, an expansion chamber having a floor forming an expansion surface for reactor-meltdown products, and a bulkhead being disposed between the antechamber and the expansion chamber and being destructible by the reactor-meltdown products. The bulkhead has a plurality of parts including at least one part being thermally destructible by the reactor-meltdown products. The at least one part is joined to the other parts for clearing a flow path for the reactor-meltdown products from the antechamber into the expansion chamber upon a destruction of the at least one part.

Device for collecting reactor-meltdown products from a reactor pressure

A nuclear reactor facility has a collecting chamber for a core melt, a coolant tank and a coolant connecting line having an inlet end connected to the coolant tank and an outlet end protruding into the collecting chamber and having an outlet cross section. A closing device at the connecting line which opens as a function of temperature for initiating cooling of the core melt includes a closing member disposed at the outlet end of the connecting line for normally tightly closing the outlet end. The closing member has a temperature-dependent opening element for tripping clearance of at least a portion of the outlet cross section of the connecting line upon thermal action by the core melt to direct the coolant from the coolant tank, through the connecting line and into the collecting chamber. The opening element being a plastic block which thermally insulates the coolant, and is corrosion-resistant.

Closing device for initiating cooling for a core melt

A device for collecting reactor-meltdown products from a reactor pressure vessel includes an expansion chamber for receiving the reactor-meltdown products and for receiving a coolant, such as cooling water, for cooling the reactor-meltdown products spreading in the expansion chamber. The expansion chamber is disposed laterally of the reactor pressure vessel and has a floor and a cooling system in the floor.

Device for collecting and cooling reactor-meltdown products

A nuclear reactor has a core and a pressure vessel with a wall and an interior. A pressure relief responding as a function of temperature is provided in the case of insufficient core cooling (due to a highly improbable failure of the cooling devices and emergency cooling devices). A safety device protecting against overpressure failure of the pressure vessel upon insufficient cooling of the core includes a pressure pipe passing pressure-tightly through the wall and extending into the interior of the pressure vessel. The pressure pipe has at least one pressure compensation opening formed therein in the interior of the pressure vessel and has a fusible sealing body sealing the pressure compensation opening. The fusible sealing body is formed of a melting solder melting at a limit temperature, such as 600.degree. to 700.degree. C., and unblocking the pressure compensation opening, but keeping the pressure compensation opening sealed during normal operation. The pressure pipe in particular is a blow-off pipe with a pressure relief opening. However, the pressure pipe can also be a pressure control pipe, with which a blow-off valve provided outside the vessel can be triggered for reducing the system pressure.

Safety device protecting against overpressure failure of a nuclear

A nuclear reactor has a pressure vessel with an interior, a coolant conducting surface, such as a wall of the pressure vessel or a line passing through the wall of the pressure vessel, a pressure relief line, and a core. A safety device which protects the pressure vessel against overpressure failure upon inadequate cooling of the core includes a pressure relief valve being pressure-tightly inserted into the coolant conducting surface and having a seat, a closure element normally disposed on the seat for blocking a flow from the interior of the pressure vessel to the pressure relief line, an abutment, and a valve closing spring holding the closure element and being supported against the abutment. A force transmission element holds the abutment and has an end facing away from the abutment. A detent is disposed in the pressure vessel and fixes the end of the force transmission element. The detent is releasable in dependence on a given threshold temperature, for example 700.degree. C., for freeing the abutment and lifting the closure element off the seat as a result of a pressure differential.

Safety device protecting a nuclear reactor pressure vessel against

A nuclear reactor includes a pressure vessel enclosing a plenum, a core in the pressure vessel, a pressure-tight encapsulation in the pressure vessel communicating with the plenum, and control members passing through the encapsulation and having first and second control member segments. The second control member segment has an absorber part to be at least partly inserted into and retracted out of the core for controlling reactivity. The first control member segment has an outer drive part. A control drive is associated with the outer drive part for adjusting the control member along the longitudinal direction thereof. An antieject device for restraining ejection of the control member out of the pressure vessel due to a leak at the encapsulation includes a rod coupling having a disengageable coupling catch interconnecting the first and second control member segments and remaining in engagement during normal control motion of the control member and means for unlocking the coupling catch. After disconnection the second control member segment and the absorber part remain in the core for assuming a position fully inserted into the core.

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Albstadt, Germany

Gerhard Hau