Abstract: A transport/storage container for heat-generating nuclear-fuel elements has spaced inner and outer side walls defining an annular space extending along an axis and having upper and lower ends. A cover is provided at the upper end and a floor at the lower end. A plurality of axially extending and angularly spaced heat-conducting metal tubes each have an inner wall section bearing in surface contact on an outer surface of the inner side wall and an outer wall section bearing in surface contact on an inner surface of the outer side wall. A concrete mass fills the space.

Abstract: A lifting lug for a nuclear-waste container has a tubular body having an inner end formed with a flange adapted to be bolted to the container and a transverse wall set in and tightly fitted to a smaller-diameter outer end of the tubular body. The wall is a separate piece from the body and is press-fitted to the tubular body. The wall is mounted at a load point of the lifting lug. In addition the wall is formed of a disk and/or a ring, typically as one unitary piece with the disk and ring spaced from each other.

Abstract: A lifting lug for a nuclear-waste container has a tubular body having an inner end formed with a flange adapted to be bolted to the container and a transverse wall set in and tightly fitted to a smaller-diameter outer end of the tubular body. The wall is a separate piece from the body and is press-fitted to the tubular body. The wall is mounted at a load point of the lifting lug. In addition the wall is formed of a disk and/or a ring, typically as one unitary piece with the disk and ring spaced from each other.

Abstract: The invention relates to a method for producing a container designed to transport and store radioactive material. The invention further relates to a container which is used to transport and store radioactive material. First and foremost, claim is laid to the selection of a heavy concrete and a special technique for inserting the heavy concrete between metall walls.

Abstract: A storage/transport container for radioactive material has a metallic outer shell, a metallic inner shell concentrically received in the outer cell and defining therewith an annular space, and an annular and continuous heat-conductive meander strip in the space. The strip is formed unitarily with a plurality of angularly spaced inner segments engaging the inner shell, respective angularly spaced outer segments engaging the outer shell, and respective generally radially extending webs extending between the inner and outer segments.

Abstract: A storage/transport container for radioactive material is made by first subdividing a chamber formed between an inner shell and an outer shell into first and second compartments by means of a foraminous partition having a predetermined maximum mesh size. Then an aggregate of a predetermined minimum particle size greater than the predetermined maximum mesh size is introduced into one of the compartments and a suspension of cement and water is introduced into the first compartment such that the aggregate remains in the one compartment and the cement and water flow through the partition into the second compartment. Normally the aggregate and the suspension are both introduced into the same compartment.

Abstract: A transport/storage container for spent nuclear-fuel elements has spaced inner and outer side walls defining an annular space extending along an axis, a cover at one end of the side walls, a floor at an opposite end of the side walls, and a plurality of heat-conducting elements in the space and each having one edge fixed, for instance by welding or bolting, to one of the side walls and an opposite edge bearing radially elastically on the other of the side walls.

Abstract: A storage/transport container for radioactive material is made by first subdividing a chamber formed between an inner shell and an outer shell into first and second compartments by means of a foraminous partition having a predetermined maximum mesh size. Then an aggregate of a predetermined minimum particle size greater than the predetermined maximum mesh size is introduced into one of the compartments and a suspension of cement and water is introduced into the first compartment such that the aggregate remains in the one compartment and the cement and water flow through the partition into the second compartment. Normally the aggregate and the suspension are both introduced into the same compartment.

Abstract: A storage/transport container for radioactive material has a metallic outer shell, a metallic inner shell concentrically received in the outer cell and defining therewith an annular space, and an annular and continuous heat-conductive meander strip in the space. The strip is formed unitarily with a plurality of angularly spaced inner segments engaging the inner shell, respective angularly spaced outer segments engaging the outer shell, and respective generally radially extending webs extending between the inner and outer segments.

Abstract: A transport/storage container holding spent radioactive fuel elements is cooled by withdrawing gases from inside the container to create a subatmospheric pressure therein, feeding coolant water from a reservoir into the container, withdrawing steam from the container, and condensing the steam outside the container into condensate water. A common pump is used both to withdraw gases and steam from the container. The steam is condensed by contacting it with water drawn from the reservoir. In addition the water drawn from the reservoir is passed countercurrent to the steam in a condenser and the condensate water is fed back to the reservoir.