The invention relates to a nuclear power plant including a containment vessel including a reactor pressure vessel for receiving fissionable nuclear fuel, an aerosol filter stage a pressure relief conduit through which a gas volume flow which is filtered in the aerosol filter stage is releasable to ambient through a pass through opening in the containment vessel, and an iodine filter stage through which the gas volume flow that is filtered in the aerosol filter stage is filterable before being released to the ambient, wherein the iodine filter stage is arranged within the containment vessel, characterized in that the aerosol filter stage and the iodine filter stage are connected with one another so that transferring the gas volume flow from the aerosol filter stage to the iodine filter stage is performed essentially at an identical pressure level.

A liquid phase catalytic exchange column with a catalyst is configured to receive hydrogen gas. The system uses the catalyst to exchange the hydrogen gas with the tritiated source yielding HT gas and tritiated water. The system monitors tritium content of the tritiated water. When a predetermined tritium level is detected, the tritiated water is released. The system also includes a gaseous permeation system comprising a permeable barrier for the selective extraction of gases.

A liquid phase catalytic exchange column with a catalyst is configured to receive hydrogen gas. The system uses the catalyst to exchange the hydrogen gas with the tritiated source yielding HT gas and tritiated water. The system monitors tritium content of the tritiated water. When a predetermined tritium level is detected, the tritiated water is released. The system also includes a gaseous permeation system comprising a permeable barrier for the selective extraction of gases.

A sparger includes a main pipe connecting inside and outside of a water tank having a storage space therein for storing cooling water, so as to define a flow path through which steam and air containing radioactive materials generated outside the water tank are discharged into the cooling water, a header part connected to one end portion of the main pipe located in the storage space, and having a storage chamber in which the steam and air transferred through the main pipe are collected, and a plurality of discharge nozzles disposed in a spacing manner, each having inlet and outlet formed on one end located in the storage chamber and another end located in the storage space, respectively, to discharge the steam and air from the storage chamber to the storage space, and at least some of the plurality of discharge nozzles protruding from the header part by different lengths.

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.

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.

An unmanned aerial vehicle may include a GPS configured to provide location coordinates for the unmanned aerial vehicle during flight and an ionization filter configured to trap radioactive particles. The unmanned aerial vehicle includes a radiation detector configured to measure radiation emitted from the trapped radioactive particles, and a memory device configured to store and associate the GPS coordinates and the measured radiation.

An unmanned aerial vehicle may include a GPS configured to provide location coordinates for the unmanned aerial vehicle during flight and an ionization filter configured to trap radioactive particles. The unmanned aerial vehicle includes a radiation detector configured to measure radiation emitted from the trapped radioactive particles, and a memory device configured to store and associate the GPS coordinates and the measured radiation.

A dry FCVS for a nuclear reactor containment is provided. The dry FCVS includes a housing and a round and/or elongated aerosol filter inside the housing for removing contaminant aerosols from gas passing through the housing during venting of the containment. The housing includes at least one inlet portion configured for directing gas into the aerosol filter during the venting of the containment and an outlet portion for gas filtered by the aerosol filter during the venting of the containment. The dry filtered containment venting system is arranged and configured such that when a flow of gas through the outlet portion is closed off at least one of convective, radiant and conductive heat transfer removes decay heat of aerosols captured in the aerosol filter.

A dry FCVS for a nuclear reactor containment is provided. The dry FCVS includes a housing and a round and/or elongated aerosol filter inside the housing for removing contaminant aerosols from gas passing through the housing during venting of the containment. The housing includes at least one inlet portion configured for directing gas into the aerosol filter during the venting of the containment and an outlet portion for gas filtered by the aerosol filter during the venting of the containment. The dry filtered containment venting system is arranged and configured such that when a flow of gas through the outlet portion is closed off at least one of convective, radiant and conductive heat transfer removes decay heat of aerosols captured in the aerosol filter.