The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

A gas stripper system for purification of a primary coolant contaminated in cooling a nuclear reactor is provided. The gas stripper system includes a gas stripper column and a condenser arrangement. The column is adapted to receive the liquid phased contaminated primary coolant. The column defines top, bottom and middle sections and includes a distributor member, a re-boiler member and a separation member disposed therealong. The distributor member, a re-boiler member and a separation member with structured packing are configured such that maximum contact between the liquid phased primary coolant and gaseous phased primary coolant is made. Moreover, the condenser arrangement is configured to the gas stripper column to receive and condense the vapour phased primary coolant.

A gas stripper system for purification of a primary coolant contaminated in cooling a nuclear reactor is provided. The gas stripper system includes a gas stripper column and a condenser arrangement. The column is adapted to receive the liquid phased contaminated primary coolant. The column defines top, bottom and middle sections and includes a distributor member, a re-boiler member and a separation member disposed therealong. The distributor member, a re-boiler member and a separation member with structured packing are configured such that maximum contact between the liquid phased primary coolant and gaseous phased primary coolant is made. Moreover, the condenser arrangement is configured to the gas stripper column to receive and condense the vapour phased primary coolant.

The present invention relates to an apparatus for treating a spent ion exchange resin, the apparatus including: a graphite reactor for receiving a spent ion exchange resin including a radionuclide-containing ion exchange group therein; a graphite heater for heating the spent ion exchange resin; an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; and a halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group, and to a method for treating a spent ion exchange resin, the method including steps of (A) drying a spent ion exchange resin including a radionuclide-containing ion exchange group; (B) producing a compound derived from the radionuclide-containing ion exchange group by separating the radionuclide-containing ion exchange group from the dried spent ion exchange resin; (C) carbonizing the spent ion exchange resin from which the radionuclide-containing ion exchange group is separated; and (D) converting a compound derived from the radionuclide-containing ion exchange group into a radionuclide-containing halide, in which steps (A) to (D) are performed in the same graphite reactor.

The present invention relates to an apparatus for treating a spent ion exchange resin, the apparatus including: a graphite reactor for receiving a spent ion exchange resin including a radionuclide-containing ion exchange group therein; a graphite heater for heating the spent ion exchange resin; an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; and a halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group, and to a method for treating a spent ion exchange resin, the method including steps of (A) drying a spent ion exchange resin including a radionuclide-containing ion exchange group; (B) producing a compound derived from the radionuclide-containing ion exchange group by separating the radionuclide-containing ion exchange group from the dried spent ion exchange resin; (C) carbonizing the spent ion exchange resin from which the radionuclide-containing ion exchange group is separated; and (D) converting a compound derived from the radionuclide-containing ion exchange group into a radionuclide-containing halide, in which steps (A) to (D) are performed in the same graphite reactor.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

One aspect of the invention provides a system for treating wastestream, particularly a liquid or aqueous radwaste, for safe disposal and, in final processing, converting it into one or both forms including an aqueous form for safe discharge to the environment and a solidified form for safe disposal. Another aspect provides the capacity to employ a step where a specific target element strategy can be set up synchronizing sorbent substance choices and multiple recycle options to remove target substances from wastestream as a part of its Sorption or Powder Sorbent Isotopic Reduction step (II). Other steps cooperate with Sorption step (II) including Oxidation (I) to inactivate or destroy existing chelants, Solid-Liquid separation (III), and Selective Ion Exchange (IV) to deliver the wastestream to final processing. Still further aspects of the invention address the recovery and safe handling of substances such as C-14 (.sup.14C); and also address treating wastestream and removing .sup.14C and water of hydration and forming dry solids for disposal, recycle or other use, such as, for example, granular, pellet or powder waste formation or product; and related special drying means for bringing this about.

One aspect of the invention provides a system for treating wastestream, particularly a liquid or aqueous radwaste, for safe disposal and, in final processing, converting it into one or both forms including an aqueous form for safe discharge to the environment and a solidified form for safe disposal. Another aspect provides the capacity to employ a step where a specific target element strategy can be set up synchronizing sorbent substance choices and multiple recycle options to remove target substances from wastestream as a part of its Sorption or Powder Sorbent Isotopic Reduction step (II). Other steps cooperate with Sorption step (II) including Oxidation (I) to inactivate or destroy existing chelants, Solid-Liquid separation (III), and Selective Ion Exchange (IV) to deliver the wastestream to final processing. Still further aspects of the invention address the recovery and safe handling of substances such as C-14 (.sup.14C); and also address treating wastestream and removing .sup.14C and water of hydration and forming dry solids for disposal, recycle or other use, such as, for example, granular, pellet or powder waste formation or product; and related special drying means for bringing this about.

The present invention provides a system for evaporating a radioactive fluid, a method for the synthesis of a radiolabelled compound including this system, and a cassette for the synthesis of a radiolabelled compound comprising this system. The present invention provides advantages over known methods for evaporation of a radioactive fluid as it reduces drastically the amount of radioactive gaseous chemicals that are released in the hot cell. It is gentler and more secure compared to the known process and provides access to radiosyntheic processes that may not been acceptable for safety reasons related to release of volatile radioactive gases during evaporation. In addition, the process yields are higher because the radioactive volatiles are labelled intermediate species.