Abstract: A shock absorber for an end of a steel or cast-iron container for the transport of spent-fuel elements is in the form of a casing with a recess receiving the end of the container and having, in turn, a stepped-pyramid element which decreases in wall thickness from the region surrounding the container end of a free end of the stepped pyramid.

Abstract: A transport/storage container for spent nuclear-fuel elements has a vessel having a side wall with an inner surface defining an interior extending along an axis and a plurality of like basket sections forming a stack extending substantially a full axial length of the interior and forming a plurality of axial full-length rectangular-section wells adapted to receive the spent fuel elements. Each of the basket sections is formed of two long light-metal neutron-absorbing plates crossing each other, each having a pair of outer ends directly engaging the inner surface of the side wall in heat-transmitting contact therewith, and subdividing the interior at the respective section into a plurality of segments. A plurality of short light-metal neutron absorbing plates are fitted together in each of the segments and form with the main plates of the respective section rectangular-section axially throughgoing openings forming the wells with the plates of the other sections.

Abstract: The invention concerns an underground storage facility for the initial storage of waste transported in containers (34, 36), in particular radioactive waste such as spent fuel elements. The store has transport galleries (10) giving access to storage galleries (12) for storage of the waste. In order to ensure, among other things, safe storage and ease of introduction and transfer of the waste, the invention proposes that the storage gallery (12) runs underneath the transport gallery (10) and is separated from it by a floor (14), designed for the transport of the waste, with closable openings (18) for the introduction and removal of the waste.

Abstract: A method and apparatus for separating the fuel rods (15) in a fuel element 8), whereby the former are retained in a bird cage arrangement (16, 18) between a head piece (19) and a foot piece (19'). The fuel elements (8) is located on a support table (6) with the help of a clamping arrangement (10). Before the fuel rods can be separated, the head piece and the foot piece are removed. In order to simplify removal of the fuel rods from the fuel element, to save space, and to minimize any risk of breakage after removal of the head piece (19) and the foot piece (19'), the bird cage arrangement (16,18) is progressively stripped from one layer of fuel rods to the next and from around the fuel rods. The exposed fuel rods are then lifted out of the fuel element (8) layer by layer and reshuffled in a more compact arrangement. A cutting tool (24), provided with a cutting disk head (26), is used to strip and separate the fuel rods with the help of a grappler (28).

Abstract: The invention concerns a depository for radioactive waste and spent fuel cells comprising a concrete storage block in which several vertical storage and cooling channels are provided for accommodating the radioactive waste and the fuel cells. In order to provide an improved and safer concrete depository vis-a-vis the state of the art, the storage block is composed of several concrete blocks disposed beside and above one another. In the concrete blocks there are several vertical channels. The aligned channels of several concrete blocks placed on top of one another form storage and cooling channels for accommodating tubular storage containers for the radioactive waste and radioactive spent fuel cells. An annular gap is left for cooling air between the outer wall of the storage containers and the inner wall of the storage and cooling channels.

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a transportable fuel element container which is suitable for storage and filled with spent nuclear reactor fuel elements. The clear interior dimensions of the concrete shielding housing are somewhat larger than the outer dimensions of the container. During its temporary storage the fuel element container must be monitored with suitable measuring instruments. In order to make the monitoring as simple as possible, measuring probes are arranged on the inner wall surface of the shielding wall of the concrete shielding housing. The measuring probes are embedded in the concrete and are already in place and ready for use before the fuel element container is loaded into the concrete shielding housing.

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a transportable fuel element container which is suitable for storage and filled with spent nuclear reactor fuel elements. The clear interior dimensions of the concrete shielding housing are somewhat larger than the outer dimensions of the container. At least one air inlet opening is provided at the lower region of the concrete shielding housing and, at the highest location of the housing, there is provided an air outlet opening. The air outlet opening is covered by means of a roof-like cover arranged in spaced relationship to the concrete shielding housing. The air outlet opening is surrounded by plates or metal strips or the like which are securely mounted to the housing and extend upwardly in the direction perpendicular to the housing. The upper edge of these plates terminate at a small distance from the roof-like cover.

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a fuel element container filled with spent nuclear reactor fuel elements. The container is suitable for transport and storage. The clear interior dimensions of the concrete shielding housing are somewhat larger than the outer dimensions of the fuel element container. The concrete shielding housing includes a pallet-type base and in the lower region of the housing there is provided at least one air inlet opening and in the upper region of the housing there is provided at least one air outlet opening. To prevent an uncontrolled conduction of moisture away from the interior of the housing to the ground or to the floor of a storage area or building, there is provided a collection pan arranged under the base plate of the pallet-like base. At least one axial bore extends clear through the base plate of the pallet-like base.

Abstract: The invention is directed to a concrete shielding housing for receiving and storing a transportable fuel element container which is suitable for storage and filled with spent nuclear reactor fuel elements. The outer dimensions of the fuel element container are somewhat smaller than the clear interior dimensions of the concrete shielding housing. The concrete shielding housing includes a pallet-like base which can be moved about from one location to another with the aid of a suitable vehicle such as a fork-lift truck. The housing also includes the concrete shielding wall placeable upon the base, and a cover which can be placed atop the upper end of the concrete shielding wall. At least one air inlet opening is provided at the lower region of the concrete shielding housing and, at the upper region thereof, there is provided at least one air outlet opening.

Abstract: The invention is directed to a dry storage facility for storing radioactive materials such as irradiated nuclear reactor fuel elements. The radioactive materials release heat generated by the radioactive decay and are held in gas-tight storage containers. The dry storage facility includes several storage modules for receiving the storage containers. The storage modules are arranged in the enclosure of the dry storage facility which can be in the form of a secure building or an underground storage cavern. A transport passageway extends alongside of the storage modules and a transport apparatus is arranged so as to be movable along this passageway. The storage containers are cooled in the storage modules by natural convection which is direct or indirect.

Abstract: The invention concerns a device for the receiving, moving and radiation-shielding of vessels filled with expended reactor fuel elements. The device consists of a protective container having a base, a cylindrical protective jacket and a cover made from concrete. At the lower rim of the jacket there are lateral air ducts which open into the annular space between protective jacket and fuel element vessel. In the area of the upper jacket edge, lateral air outlet ducts are provided. For facilitating the loading of the device with fuel element containers and its transportation, the base is constructed in the form of a separate movable pallet. The fuel element container can be placed on this pallet, and the protective jacket over it. The air outlet ducts in the area of the cover are arranged in an inclined or angular fashion. The base is provided with a raised center platform for supporting the fuel element vessel.