Abstract: A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid.

Abstract: A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid.

Abstract: A containment vessel of a boiling-water nuclear power plant and a method of operating a condenser in a nuclear power plant, include a drain pipe which connects a top region of the containment vessel to a condensing chamber disposed in the containment vessel. The drain pipe draws off noncondensible gases from the surroundings of a building condenser in the containment vessel and thus maintains reliability of performance of the building condenser. The noncondensible gases flow automatically into the condensing chamber through the drain pipe. As a result, the building condenser may have a simple and cost-effective structure.

Abstract: A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid.

Abstract: A containment of a nuclear power plant has a pressure chamber, a condensation chamber, and a substantially vertically running condensation tube. The upper end of the tube is connected to the pressure chamber and the lower end of the tube is immersed in a cooling liquid in the condensation chamber. The lower end of the condensation tube has an elbow and an outlet nozzle. The elbow has an elbow angle which is such that the lower end of the elbow is immersed obliquely in the cooling liquid in the condensation chamber, and the outlet nozzle has an outlet opening which is substantially shielded with respect to the base of the condensation chamber. This renders it possible to significantly reduce the pressure loads on the base and the walls of the condensation chamber in the event of an emergency.

Abstract: A nuclear facility contains a flood tank, which is provided for holding a cooling liquid, a condensation chamber, and an overflow device, which leads from the flood tank to the condensation chamber and which serves to discharge excess cooling liquid. The overflow device is provided for separating gas components out from the excess cooling liquid. In certain operating states, the cooling liquid of the condensation chamber and of the flood tank is circulated in a common cooling circuit and is fed, while being largely free of gas, once more into the condensation chamber via the overflow device.

Abstract: A feeding system for an absorber liquid containing a neutron poison, in particular for a quick shut-down of a nuclear reactor, has a storage container for the absorber liquid and is configured for high operational reliability with simple construction. In particular, a chemical decomposition of the absorber liquid or corrosion of the container wall of the storage container is to be excluded. For this purpose, the storage container is connected to a pressure container via an overflow line, wherein the pressure container is filled with a motive fluid.

Abstract: A nuclear facility contains a flood tank, which is provided for holding a cooling liquid, a condensation chamber, and an overflow device, which leads from the flood tank to the condensation chamber and which serves to discharge excess cooling liquid. The overflow device is provided for separating gas components out from the excess cooling liquid. In certain operating states, the cooling liquid of the condensation chamber and of the flood tank is circulated in a common cooling circuit and is fed, while being largely free of gas, once more into the condensation chamber via the overflow device.

Abstract: A containment of a nuclear power plant has a pressure chamber, a condensation chamber, and a substantially vertically running condensation tube. The upper end of the tube is connected to the pressure chamber and the lower end of the tube is immersed in a cooling liquid in the condensation chamber. The lower end of the condensation tube has an elbow and an outlet nozzle. The elbow has an elbow angle which is such that the lower end of the elbow is immersed obliquely in the cooling liquid in the condensation chamber, and the outlet nozzle has an outlet opening which is substantially shielded with respect to the base of the condensation chamber. This renders it possible to significantly reduce the pressure loads on the base and the walls of the condensation chamber in the event of an emergency.

Abstract: In order, in a pressure accumulator, to generate a required operating pressure of a fluid situated in the pressure accumulator, a heater device is provided, disposed in an upper region of the pressure accumulator. The device generates a vapor cushion and the required operating pressure. Where necessary, when the fluid flows out, the pressure in the pressure accumulator is automatically reduced after the level has fallen below a defined filling level, as a result of the vapor condensing at a cold insulating device with a high heat-accumulation capacity. The pressure accumulator is preferably used as an emergency shut-down tank or as an emergency accumulator in a nuclear power plant.

Abstract: In order to allow a reliable and passive external cooling of a reactor pressure vessel of a boiling water reactor, outside the reactor pressure vessel a differential-pressure measurement pipe is provided and has a first and a second pipe leg which are connected to one another above a critical filling level. The first pipe leg is connected at the height of the critical filling level to the interior of the reactor pressure vessel. In a normal operating state, the differential-pressure measurement pipe is filled completely with water. In the event of the undershooting of the critical filling level, the water flows automatically out of the first pipe leg. As a result, the differential pressure between the two pipe legs rises, the differential pressure being detected by a measurement device via which the flooding of the exterior is then brought about.

Abstract: In order, in a pressure accumulator, to generate a required operating pressure of a fluid situated in the pressure accumulator, a heater device is provided, disposed in an upper region of the pressure accumulator. The device generates a vapor cushion and the required operating pressure. Where necessary, when the fluid flows out, the pressure in the pressure accumulator is automatically reduced after the level has fallen below a defined filling level, as a result of the vapor condensing at a cold insulating device with a high heat-accumulation capacity. The pressure accumulator is preferably used as an emergency shut-down tank or as an emergency accumulator in a nuclear power plant.

Abstract: In order to allow a reliable and passive external cooling of a reactor pressure vessel of a boiling water reactor, outside the reactor pressure vessel a differential-pressure measurement pipe is provided and has a first and a second pipe leg which are connected to one another above a critical filling level. The first pipe leg is connected at the height of the critical filling level to the interior of the reactor pressure vessel. In a normal operating state, the differential-pressure measurement pipe is filled completely with water. In the event of the undershooting of the critical filling level, the water flows automatically out of the first pipe leg. As a result, the differential pressure between the two pipe legs rises, the differential pressure being detected by a measurement device via which the flooding of the exterior is then brought about.

Abstract: An apparatus and a method for the superheating of steam is used, in particular, for converting saturated steam into hot steam in the field of nuclear energy generation. As a result of at least partial conversion of pressure energy of the steam into kinetic energy, in particular into kinetic energy of a rotational flow, the steam cools and condensate and residual steam are generated. After the condensate has been separated from the residual steam, the latter is superheated as a result of a reduction of its kinetic energy and is converted into hot steam.

Abstract: A condensation vessel for the measurement of steam pressure includes a steam zone, a steam line which opens in the steam zone at an entrance, a condensate zone which is directly adjacent the steam zone and geodetically below the entrance, and a discharge device which is connected to the steam zone and which serves for a discharge of steam and noncondensable gases from the condensation vessel. A method for operating the condensation vessel includes condensing steam which contains an increased fraction of a noncondensable gas, in particular radiolysis gas, out of the steam zone. The gas is led out of the condensation vessel in dissolved form through the discharge device, with the result that the risk of faulty measurement is largely ruled out, since virtually no gas is dissolved in the condensate within the condensate zone. The condensation vessel can be installed in a simple way, even in the course of retrofitting, for measuring the filling level of a reactor pressure vessel.

Abstract: According to one embodiment, a fuel assembly includes a bundle of fuel rods. Approximately mutually parallel upright webs extend between the fuel rods in a plane approximately perpendicular to the fuel rods. The webs have upper edges and tabs on the upper edges. The tabs have ends and the tabs are twisted continuously more severely toward the ends away from the webs. According to another embodiment, the fuel assembly includes a bundle of fuel rods defining flow channels and an axis approximately parallel to the fuel rods. Lengthwise webs extend approximately parallel to one another between the fuel rods in a first plane extending approximately perpendicular to the fuel rods. Crosswise webs, which extend approximately perpendicularly to the lengthwise webs, are disposed in a second plane approximately parallel to the first plane and join the lengthwise webs to one another between the fuel rods. Tabs are twisted about the axis and disposed in the flow channels.