Abstract: An overpack cask for reversibly receiving, handling and transporting a repository container for spent nuclear material is disclosed, and the overpack cask comprises a tubular cask shell defining a receiving cavity for reversibly receiving a repository container therein, a first cask cover providing a sealing closure of the receiving cavity at a first axial end of the tubular cask shell and a second cask cover providing a sealing closure of the receiving cavity at a second axial end of the tubular cask shell opposite to the first axial end. At least the first cask cover is removable from the tubular cask shell to uncover a first opening of the tubular cask shell at the first axial end for loading and/or unloading a repository container into and from the receiving cavity, respectively.

Abstract: The present invention relates to a method for separating cesium and technetium from radioactive waste, which method comprises the sublimation of cesium pertechnetate, and an apparatus for carrying out this method. The separation includes the steps of obtaining the two elements cesium and technetium together from the waste and subsequently separating the two elements from each other. The aim of the present invention is to significantly reduce the activity of radioactive solid waste and to use the obtained radionuclides in an economical and technical manner. Additionally, the method allows elements of cesium and technetium to be separated directly from the operation of a vitrification, sintering, drying, combustion, cementing, or calcinating plant, thus obviating additional problems when carrying out the process.

Abstract: A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin.

Abstract: A process for the recovery of a radioisotope from a waste resin of a nuclear power plant comprises the steps of: a) treating a waste resin loaded with at least one radioisotope with an organic acid or alkaline compound to release the at least one radioisotope and to obtain a process solution containing the at least one radioisotope; b) separating the at least one radioisotope from the process solution through a reaction specific to the radioisotope so as to obtain a treated process solution depleted of the at least one radioisotope, wherein said depleted process solution comprises the organic acid or alkaline compound and optionally a non-reacted radioisotope; c) reacting the organic acid or alkaline compound in the depleted process solution from step b) by thermal and/or photochemical oxidation to form gaseous reaction products; and d) reloading the waste resin with the reacted process solution from step c) to bind the non-reacted radioisotope on the waste resin.

Abstract: To manufacture shaped bodies (10) filled with powder (22) for introduction into the reactor core of a commercial nuclear power reactor a plate made of a metal and/or metalloid is provided with one or more blind holes (14), the blind holes (14) are filled with powder (22), the blind holes (14) filled with powder (22) are reversibly sealed and shaped bodies are cut from the plate so that each blind hole (14) filled with powder (22) is surrounded by a shell made of a metal or metalloid. The powder-filled shaped bodies (10) are used in a ball measuring system for commercial nuclear power reactors and/or for the generation of radionuclides in said reactors.

Abstract: The invention relates to a lance for removing deposits adhering to the tube sheet of a steam generator, comprising a flexible strip which is introducing into intermediate tube areas of the steam generator, which has a cleaning head at the free end of the strip, and which comprises at least one water hose that is used to supply a flow of water to the cleaning head. In a use situation, the cleaning head comprises a working face which faces the tube sheet or deposits present thereon, an outlet opening which is fluidically connected to the water hose and opens into the working face, and a mechanical tool which acts on the deposits and removes material.

Abstract: A component for conducting or receiving a fluid, in particular a component of a fluid-conducting line system of an industrial plant, especially of a line system of a tertiary cooling circuit of a nuclear power plant, includes a wall having a supporting structure made of a glass-fiber-reinforced plastic. Electrically insulating inner and outer protective layers are disposed on respective inner and outer surfaces of the supporting structure. An electrically conductive inner intermediate layer lies between the inner protective layer and the supporting structure and is provided with an electrical terminal. An electrically conductive outer intermediate layer lies between the outer protective layer and the supporting structure, is provided with an electrical terminal and is electrically insulated from the inner intermediate layer. A method for testing the component is also provided.

Abstract: The invention relates to a lance for removing deposits adhering to the tube sheet of a steam generator, comprising a flexible strip which is introducing into intermediate tube areas of the steam generator, which has a cleaning head at the free end of the strip, and which comprises at least one water hose that is used to supply a flow of water to the cleaning head. In a use situation, the cleaning head comprises a working face which faces the tube sheet or deposits present thereon, an outlet opening which is fluidically connected to the water hose and opens into the working face, and a mechanical tool which acts on the deposits and removes material.

Abstract: The invention relates to a method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility, wherein the oxide layer is treated with gaseous nitrogen oxide (NOx) as oxidizing agent.

Abstract: A method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility. An acidic water film is produced on the surface, the film of water is brought into contact with a gaseous acid anhydride, and the oxide layer is treated with gaseous ozone as oxidizing agent.

Abstract: A method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility. An acidic water film is produced on the surface, the film of water is brought into contact with a gaseous acid anhydride, and the oxide layer is treated with gaseous ozone as oxidizing agent.

Abstract: The invention relates to a method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility, wherein the oxide layer is treated with gaseous nitrogen oxide (NOx) as oxidizing agent.

Abstract: The radioactivity of a metal part is reduced in the process. In the method, firstly a layer of oxide is removed from the metal part using a decontamination solution. Then, an agent which has an oxidizing action and is still present is removed from the decontamination solution. As a result, a layer of the metal is removed. Since radionuclides are to be found only in the layer of the metal part which is close to the surface, the remaining metal can be scrapped in the conventional way.

Abstract: A method for controlling clocks in computer networks of a hierarchical structure includes the continual synchronization of the clock modules provided in the individual network levels to the time of a central master clock by means of messages. Time stamps are output from each clock module. Besides a time-of-day field and a date field, these time stamps contain additional information fields relating to synchronization source, synchronization type, synchronization delay, and time-of-day resolution.