Abstract: A method for pressure relief of a containment of a nuclear power plant includes heating a washing fluid in a filter disposed inside a containment at a rated heating power through a thermal bridge, with a gas-steam mixture filling the containment, prior to initial operation of the filter. The thermal bridge is rendered substantially ineffective in an operating state of the filter, leaving the washing fluid with a continuous rated heating power being negligible in terms of filtration. In a nuclear power plant having a containment, a system for pressure relief of the containment includes a filter being disposed inside the containment and having a container. At least part of the container has two walls defining a chamber between the walls. A heat-conducting fluid at least partly fills the chamber during a heating period and is at least half evaporated after attainment of an operating temperature.

Abstract: A nuclear power plant includes a containment for the retention of radioactivity having an overpressure safety outlet. A filter connected to the outlet includes a vessel for receiving a scrubbing liquid up to a given liquid level, a venturi scrubber disposed in the vessel having an outlet disposed above the given liquid level, an impact plate disposed at the outlet of the venturi scrubber for mist collection, a metal-fiber filter downstream of the venturi scrubber having at least first and second layers with a thickness of from 10 to 20 mm, the first layer being a moisture collector with a fiber thickness of from 8 to 20.mu. and the second layer being an aerosol collector with a fiber thickness of from 2 to 7.mu., and a mist collector downstream of the metal-fiber filter. The vessel has a top with a gas outlet downstream of the mist collector. A stack is connected to the gas outlet and leads to the atmosphere.

Abstract: An adsorption device for gas separation with an adsorbent includes a thermally insulated container. Adsorber tubes with a given length are vertically disposed in the container for receiving adsorbent. A heating device is adjacent the adsorber tubes. Cooling tubes are disposed alongside the adsorber tubes and extend over substantially all of the given length for receiving coolant. A gas circulation device in the container generates a gas flow encompassing the heating device, the cooling tubes and all of the given length of the adsorber tubes.

Abstract: A method and apparatus for pressure relief of a nuclear power plant includes the feeding of fluid from an outlet opening of a containment through a filter to a stack. The filter is operated with sliding pressure regulated as a function of the pressure in the containment.

Abstract: A nuclear power plant includes a containment for containing activity carriers. An outlet in the form of an excess pressure safety device leads out of the containment. A filter connects the outlet to the atmosphere. The filter includes a container, a washing fluid disposed in the container, a Venturi scrubber being integrated in the container and connected to the outlet, the container having an upper region with a gas outlet, and a stack connected to the gas outlet.

Abstract: A method for operating a nuclear reactor having reactor coolant including an exhaust gas source and an exhaust gas system connected to the exhaust gas source, the exhaust gas system having at least one compressor connected to the exhaust gas source, a gas cooler connected to the compressor, a first reducing valve connected to the gas cooler, a switching valve connected to the first reducing valve, a moisture adsorber connected to the switching valve, a delay line normally connected in parallel with the moisture adsorber, a gas loop connected between the moisture adsorber and the compressor, a flue connection set at a given pressure during normal operation, and a second reducing valve connected between the delay line and the flue connection, includes interconnecting the delay line and the moisture adsorber in series, setting the flue connection to a pressure at least twice as high as the given pressure, reversing the switching valve thus allowing the exhaust gas to pass from the moisture adsorber to the delay

Abstract: Apparatus for storing spent fuel assemblies of a nuclear reactor including a fuel-assembly transport cask having a hollow chamber for receiving therein at least one fuel assembly and having a cover for gas-tightly closing off an opening to the hollow chamber, including means for supplying a trace gas into the hollow chamber, an additional cover defining a leakage detection chamber covering the cross-section of the opening to the hollow chamber, and a measuring device for the trace gas connected to the leakage detection chamber for monitoring gas-tightness of the closure of the opening to the hollow chamber, and method for using the apparatus.