Nuclear facility and closure device for their containment
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Method for testing a fuel rod cladding tube and associated device
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Device for increasing the lifting-lowering path of a crane for transporting containers for fuel elements to a fuel element storage unit comprises a lifting tie-bar
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Safe feed system for absorber fluid containing neutron poison, for use in rapid shut-down of nuclear reactor, comprises storage container connected to pressure vessel filled with propellant fluid via overflow line
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Purifying method for the removal of depositions containing magnetit from a pressure-container of a power station
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Method to inspect the density of the fuel-bars for the fuel-elements of a boiling-water reactor
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Pumping device for nuclear installations
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Method for repairing or preventing damage to a bushing
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Fuel-element for a boiling-water reactor
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Handling and repairing unit for a nuclear reactor fuel element, comprises a shaft with an inlet and an outlet opening, a press unit, a cutting unit, and a container
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Holding and transport unit for nuclear reactor component, comprises externally accessible structural element, support element, and coupling unit
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Collection pipe for leakages, e.g. of hydrocarbon compounds, has a perforated carrier pipe with an electrically conductive layer and an outer covering layer
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Method and device for dismantling a control element of a boiling water reactor
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Method and device for determining the deviation of a along an actual path translationally guided body of a desired path
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Method for preparing a built-in part of a fuel element of a pressurized water nuclear reactor for disposal, and corresponding conditioned built-in part
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Fuel element for a boiling water nuclear reactor, comprises a foot, a sieve plate, a fuel element head and a bundle of longitudinal fuel rods
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control device
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Method for testing fuel assemblies of a boiling water reactor for leaks in their fuel rods
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Cleaning process for removal of magnetite-containing deposits from a pressure vessel of a power plant
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Method and apparatus for disposing of a fuel assembly channel of a boiling water reactor plant
