摘要:
A sealing apparatus for mitigating emissions of a hazardous gas flowing between first and second regions. A body of the apparatus includes at least one inlet, at least one outlet spaced apart from the at least one inlet, and a channel connecting the at least one inlet and the at least one outlet in fluid communication. Treatment material housed in at least a portion of the channel is adapted to treat the hazardous gas to form a conditioned gas. In use, the hazardous gas being emitted from the first region is received at the at least one inlet, and the conditioned gas is discharged to the second region at the at least one outlet. The apparatus may be used in combination with a storage container housing radioactive or other toxic waste.
摘要:
The present invention relates to a passive filtration system for a fuel handling area having a spent fuel pool in a nuclear reactor. The passive filtration system reduces a discharge into the atmosphere of particulates, such as radioactive particulates, generated in a spent fuel pool boiling event. The passive filtration system includes a discharge path, a vent mechanism positioned between the fuel handling area and the discharge path. The vent mechanism is structured to release a steam and air mixture from the fuel handling area to the discharge path. The steam and air mixture includes the particulates. The passive filtration system further includes an air filtration unit located in the discharge path and this unit has at least one passive filter. The steam and air mixture is forced through the at least one passive filter due to a differential pressure generated in the fuel handling area. The at least one passive filter traps particulates from the steam and air mixture to produce a filtered steam and air mixture that is released through a second vent mechanism into the atmosphere.
摘要:
A method of removing a radioactive material from a gas includes directing the gas through a bed of salt (112), wherein the gas includes water vapor and the radioactive material. The salt (112) constitutes more than 50 percent by weight of the bed. The method additionally includes condensing the water vapor in the bed and dissolving a portion of the salt (112) to form a salt solution. The method further includes absorbing the radioactive material into the salt solution while a remainder of the gas passes through the bed. A salt filtration system (100) configured to perform the method may be implemented as a pre-filter to an existing filter unit or as a standalone filter.
摘要:
A method for filtration of harmful gas effluents from a nuclear power plant including the steps of providing a gas effluent from a nuclear power plant, the effluent including a mixture of gases; filtering the harmful, notably radioactive elements from the gas effluent by membrane separation through at least one membrane, the membrane separation being achieved by sifting, sorption and/or diffusion; storing the filtered harmful elements in storage reservoirs, and discharging the processed gas effluent to the atmosphere.
摘要:
A membrane (210) for a method for filtration of gas effluents from an industrial installation comprising a wall including an internal surface and an external surface, said wall having pores (P) of variable dimensions in the radial direction and in the longitudinal direction of said wall.
摘要:
A methyl iodide adsorber is provided, comprising a zeolite containing at least one iodide-adsorbing metal or a compound thereof, wherein the zeolite is a hydrophobic zeolite. A use of the adsorber and a method for adsorption of methyl iodide are also specified.
摘要:
Disclosed are a reagent for testing the purification capacity of a radioactive gas in a nuclear power plant, preparation method thereof and an iodide filter testing equipment using this reagent. The reagent is prepared by mixing methyl phosphate compound or dimethyl acetal compound, acetonitrile, trimethyl chlorosilane and radioactive iodine sources and carrying out a reaction at a temperature of 20°C-50 °C under an inert gas for 10-40 min. The prepared products except methyl iodide are non-toxic or little toxic to the nuclear grade impregnated activated carbon in the iodide filter.
摘要:
This filter comprises a plurality of reservoirs (1, 2 and 3) connected in series by connecting ducts (4, 5). The flow of gaseous streams therein is subject to multiple obstacles which have the effect of effectively trapping the constituents with the highest molecular weight without substantially impeding the diffusion of the light constituents. This can be achieved through the use of internal baffles (9) or an array (6) of thinner ducts (7), for example at the entry to the filter. Possible application to the separation of hydrogen and radon produced by nuclear waste.