Gns Gesellschaft Fur Nuklear-service Mbh

Gnb Gesellschaft Fur Nuklear-behalter Mbh

Metallveredlung Gmbh & Co. Kg

Dieter Methling

Rudolf Diersch

Konrad Gluschke

Klaus G Janberg

Karl Schroder

Henning Baatz

Harry Spilker

Matthias Patzelt

Klaus-Leo Wilbuer

Hermann Stelzer

Joachim Heidenreich

The invention relates to a method for producing a coating for absorption of neutrons produced in nuclear reactions of radioactive material which can be applied in an economically feasible and simple manner, increases the effectivity of absorption, enables greater variability of base material used and variability of shape of said shielding elements and in particular the production of lighter shielding elements with at least the same absorption quality. The invention also relates to a method for producing a coating for absorption of neutrons produced in nuclear reactions of radioactive materials. At least one part of a shielding element consisting of base material is provided at its surface designed therefore with a layer made of an element with a high neutron capture section and a metallic element in a dispersion bath. Said metallic element can be deposited by electrolytic or autocatalytic means. During the coating process, a relative movement between a surface to be coated and a dispersion bath is effected at least temporarily, whereby the element with a larger neutron capture section is present in an electrically conducting compound in said dispersion bath.

Method for producing a coating for absorption of neutrons produced in nuclear reactions of radioactive materials

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.

Storage/transport container for radioactive material

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.

Making storage/transport container for radioactive material

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.

Storage/transport container for spent nuclear-fuel elements

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.

A radiation-shielding storage/transport container has a cast-iron vessel having an open end defining an end face, a steel ring engaging the end face and forming at least one annular seat, a weld unitarily bonding the ring to the end face, and a cover secured to the steel ring in the seat thereof. The cast-iron vessel is formed at its open end with an annular seat having a shoulder surface forming the end face. The weld is an aluminothermic weld that extends over the entire surface of the interface between the ring and the vessel. The ring is formed with two such seats and the cover includes an inner plug cover and an outer cover each in a respective one of the seats. The outer cover is of steel and a second peripheral weld connects the outer cover to the respective seat.

Radiation-shielding transport and storage container

The apparatus for transferring at least one radioactive object from a first into a second container comprises a lifting tool with which the radioactive object is lifted from the first container and is lowered into the second container, a container-receiving member on which the first and second containers stand spaced from each other, a movable transfer slide provided with at least two container-cover cavities for receiving and securing first and second covers sealing respective containers and a transfer cover and the other container cover and a transfer receptacle in which the lifting tool is positionable which is combined with the movable transfer cover, is positionable over a hole provided in the movable transfer slide and is accessible from below. A method of operating this apparatus for transfer of a radioactive object is provided which does not require a special hot cell or room.

Apparatus and method for transferring a radioactive object from one

A container has a massive metallic vessel whose interior is adapted to receive radioactive waste and whose mouth is formed with inner and outer spaced generally planar and annular vessel shoulders and formed therebetween with a nonplanar intermediate annular vessel surface. A massive metallic cover formed with a plug fits in the mouth and has respective inner and outer plug shoulders closely juxtaposed with the vessel shoulders and a nonplanar intermediate annular plug surface complementary to the intermediate vessel surface. An inner ring seal engages snugly between the inner shoulders. A pair of generally concentric and spaced outer ring seals engage snugly between the outer shoulders and forming an annular outer chamber therebetween. An intermediate ring seal engages snugly between the intermediate surfaces and forms therebetween and with the inner ring seal an annular inner chamber and therebetween and with the outer ring seals an intermediate chamber. The cover is formed with respective inner, intermediate, and outer passages each having one end opening into the respective chamber and another end. Valves are provided on the cover at the other ends of the passages for sampling gases therein and in the respective chambers.

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Hattingen, Germany

Dieter Methling