Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh

Kraftwerk Union Aktiengesellschaft

Deutsche Gesellschaft F',uml/u/ R Wiederaufarbeitung Von

Bernd Pontani

Helfrid Lahr

Ulrich Simon

Klaus-Dieter Werner

Franz-Wolfgang Popp

Dieter Hoffmann

Erich Ernst

The invention relates to a docking arrangement for docking a transport container to a lock opening of a radioactively charged work chamber for loading and unloading radioactive materials. In order to dock the heavy transport container precisely at the lock opening and to reliably remotely manipulate the closure cover of the container, the lock opening is covered from within the work chamber by a bell-shaped closure device which can be removed inwardly. This bell-shaped closure device is laterally displaceable in the lock opening and is resiliently journalled and therefore can align itself with respect to the docked transport container.

Docking arrangement for connecting a transport and storage container to

The invention relates to an apparatus for handling a fuel element skeleton f an irradiated nuclear reactor fuel element from which the fuel rods have been removed. The fuel element skeleton is placed horizontally in a compacting shaft of a ram-type press in order to obtain a simple and reliable compaction of the skeleton. After the compacting shaft is closed, the fuel element skeleton is compacted against a press base. The compacted fuel element skeleton is pushed out of the compacting shaft and into a transportable transfer shaft. The loaded transfer shaft is removed from the ram-type press and transported away to a transfer loading location.

Apparatus for handling a fuel element skeleton

The invention relates to a method for handling a fuel element skeleton of an irradiated nuclear reactor fuel element from which the fuel rods have been removed. The fuel element skeleton is placed horizontally in a compacting shaft of a ram-type press in order to obtain a simple and reliable compaction of the skeleton. After the compacting shaft is closed, the fuel element skeleton is compacted against a press base. The compacted fuel element skeleton is pushed out of the compacting shaft and into a transportable transfer shaft. The loaded transfer shaft is removed from the ram-type press and transported away to a transfer loading location.

Method for handling a fuel element skeleton

A double container system for transporting and storing radioactive waste erials includes an inner storage container of steel for enclosing the radioactive material to be stored in a gas-tight manner and an outer shielding container which provides for the necessary shielding effect and mechanical security with regard to handling and transportation. A neutron moderator layer is disposed in an annular gap between the outer shielding container and the inner storage container. The neutron moderate layer is made of hydrogen-bearing material, preferably polyethylene. In order to provide a good shielding effect while at the same time providing very good conduction of heat from the inside to the outside, the moderator layer includes individual rings of polyethylene which are stacked one above the other. Arranged between each two mutually adjacent ones of the polyethylene rings is a ring of a heat-conducting metal material having an H-profile when viewed in radial section. The legs of the H-profile ring embrace the sides of the two mutually adjacent polyethylene rings for fixing the latter in position.

Double container system for transporting and storing radioactive

A method and an apparatus for loading containers with individual fuel rods or fuel-rod sections of irradiated nuclear reactor fuel elements are disclosed. In order to ensure maximum safety, cleanliness and close packing when loading the containers, the fuel rods or fuel-rod sections are horizontally front-loaded into the container which is horizontally positioned. The loading aperture is located as closely as possible to the upper inner periphery of the container. Following their insertion, the fuel rods or fuel-rod sections will drop onto the inner wall surface of the container or onto the already existing pile of previously loaded fuel rods or fuel-rod sections. The container for loading with such a method has a loading aperture in the end wall thereof arranged close to the inner periphery thereof for insertion of the fuel rods or fuel-rod sectons. The apparatus for loading containers in accordance with the method disclosed includes a loading trough which is insertable into a loading aperture in the container and serves to load the fuel rods or fuel-rod sections. The loading trough is capable of being rotated about its longitudinal axis whereupon the fuel rod or fuel-rod section drops down.

Nuclear storage container for use in a method for loading the same with

A storage container is disclosed for accommodating fuel rods of disassemb irradiated nuclear reactor fuel elements. The storage container includes a circular storage space into which a cage receiving the canned fuel rods is inserted. The individual fuel-rod cans are arranged in the insert cage in the form of a circle in order to achieve a good removal of heat. Hold-down springs bear on the end faces of the cans. The radial extension of the fuel-rod cans towards the longitudinal center of the container is limited to accommodate an empty square central shaft in the middle of the insert cage.

Storage container assembly for accommodating individual fuel rods of

A method and an apparatus for loading containers with individual fuel rods r fuel-rod sections of irradiated nuclear reactor fuel elements are disclosed. In order to ensure maximum safety, cleanliness and close packing when loading the containers, the fuel rods or fuel-rod sections are horizontally front-loaded into the container which is horizontally positioned. The loading aperture is located as closely as possible to the upper inner periphery of the container. Following their insertion, the fuel rods or fuel-rod sections will drop onto the inner wall surface of the container or onto the already existing pile of previously loaded fuel rods or fuel-rod sections. The container for loading with such a method has a loading aperture in the end wall thereof arranged close to the inner periphery thereof for insertion of the fuel rods or fuel-rod sections. The apparatus for loading containers in accordance with the method disclosed includes a loading trough which is insertable into a loading aperture in the container and serves to load the fuel rods or fuel-rod sections. The loading trough is capable of being rotated about its longitudinal axis whereupon the fuel rod or fuel-rod section drops down.

Method for loading fuel rods into a container

Method and apparatus for loading fuel rods into a container

In a blow-off device for limiting excess pressure in nuclear power plants, a condensation tube disposed so that a lower outlet end thereof is immersed in a volume of water in a condensation chamber having a gas cushion located in a space above the volume of water, and an upper inlet end of the condensation tube extends out of the volume of water and is connectible to a source of steam that is to be condensed or a steam-air mixture, the outlet end of the tube, for stabilizing the condensation, being provided with a base member at the mouth of the tube for limiting steam flows discharging in axial direction of the tube and being formed with lateral outlet openings for subdividing the steam flow and the bubbles produced in the volume of water, the base member at the tube mouth being formed at a conical insert member having a base fastened to the condensation tube in vicinity of the mouth thereof and having an apex extending into the tube mouth, the lateral outlet openings being disposed at least within the axial range of the insert member.

Condensation tube for a blow-off device for limiting excess pressure in

In a blow-off device for limiting excess pressure in nuclear power plants, a condensation tube disposed so that a lower outlet end thereof is immersed in a volume of water in a condensation chamber having a gas cushion located in a space above the volume of water, and an upper inlet end of the condensation tube extends out of the volume of water and is connectible to a source of steam that is to be condensed or a steam-air mixture, the outlet end of the condensation tube being further provided with a base member at the mouth of the outlet end for limiting steam flows discharging in axial direction of the tube, and being formed with lateral openings subdividing the steam flow and bubbles produced in the volume of water, the lateral outlet openings being formed of slots widening toward the end of the condensation tube, the slots being distributed over the periphery of the outlet end of the condensation tube.

In a blow-off device for limiting excess pressure in nuclear power plants, at least one condensation tube disposed so that a lower outflow end thereof is immersed in a volume of water in a condensation chamber having a gas cushion located in a space above the volume of water, and an upper inflow end of the condensation tube extends out of the volume of water and is connectible to a source of steam that is to be condensed or a steam-air mixture, the outflow end of the condensation tube, for stabilizing the condensation being provided with an assembly of wall parts forming passageways extending in axial direction for subdividing the steam flow and bubbles produced in the volume of water, the passageways of the assembly of wall parts being stepped in axial direction at both axial ends of the assembly of wall parts.

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Alzenau, Germany

Bernd Pontani