Chromatography columns for the purification of eluates from .sup.68Ge/.sup.68Ga generators comprising silica as stationary phase and purification processes that use said columns are described.

Chromatography columns for the purification of eluates from .sup.68Ge/.sup.68Ga generators comprising silica as stationary phase and purification processes that use said columns are described.

A preparation method of a bacterial cellulose-defective molybdenum disulfide (BC-MoS.sub.2-x) heterojunction material for treating radioactive wastewater is provided, including: preparing bacterial cellulose by the in situ growth technology of Acetobacter xylinum, and freeze-drying to obtain dried bacterial cellulose; carbonizing the dried bacterial cellulose to obtain carbonized bacterial cellulose; dispersing the carbonized bacterial cellulose into deionized water under an ultrasonic treatment; then adding thiourea and Na.sub.2MoO.sub.4.2H.sub.2O, dissolving under an ultrasonic treatment to obtain a reaction mixture, subjecting the reaction mixture to a hydrothermal reaction to obtain a BC-MoS.sub.2 heterojunction; and calcining the BC-MoS.sub.2 heterojunction in a tube furnace with an Ar/H.sub.2 atmosphere to obtain the BC-MoS.sub.2-x heterojunction.

A preparation method of a bacterial cellulose-defective molybdenum disulfide (BC-MoS.sub.2-x) heterojunction material for treating radioactive wastewater is provided, including: preparing bacterial cellulose by the in situ growth technology of Acetobacter xylinum, and freeze-drying to obtain dried bacterial cellulose; carbonizing the dried bacterial cellulose to obtain carbonized bacterial cellulose; dispersing the carbonized bacterial cellulose into deionized water under an ultrasonic treatment; then adding thiourea and Na.sub.2MoO.sub.4.2H.sub.2O, dissolving under an ultrasonic treatment to obtain a reaction mixture, subjecting the reaction mixture to a hydrothermal reaction to obtain a BC-MoS.sub.2 heterojunction; and calcining the BC-MoS.sub.2 heterojunction in a tube furnace with an Ar/H.sub.2 atmosphere to obtain the BC-MoS.sub.2-x heterojunction.

Provided is an adsorbent for removal of iodide ions and iodate ions, which exhibits excellent adsorption performance of iodide ions and iodate ions. An adsorbent according to the present invention comprises cerium(IV) hydroxide and a poorly soluble silver compound. It is preferable that the content of cerium(IV) hydroxide is 50% by mass or more and 99% by mass or less, and the content of the poorly soluble silver compound is 1% by mass or more and 50% by mass or less. It is also preferable that the poorly soluble silver compound is at least one selected from silver zeolite, silver phosphate, silver chloride, and silver carbonate.

Provided is an adsorbent for removal of iodide ions and iodate ions, which exhibits excellent adsorption performance of iodide ions and iodate ions. An adsorbent according to the present invention comprises cerium(IV) hydroxide and a poorly soluble silver compound. It is preferable that the content of cerium(IV) hydroxide is 50% by mass or more and 99% by mass or less, and the content of the poorly soluble silver compound is 1% by mass or more and 50% by mass or less. It is also preferable that the poorly soluble silver compound is at least one selected from silver zeolite, silver phosphate, silver chloride, and silver carbonate.

The invention relates to a method for removing a chemical substance from human excreta, such as faeces and urine, comprising the following steps of: providing a toilet for a person from whose excreta the chemical substance must be removed; releasably connecting a filtering device to the toilet, wherein the filtering device comprises at least one removable cartridge with a filter; transporting the excreta by means of a transport screw from the toilet toward the filter in the cartridge, wherein pressure is exerted on the excreta by means of a plunger; filtering the chemical substance out of the excreta in situ using the filtering device; periodically replacing the at least one cartridge; and processing the replaced cartridge. The invention also relates to a filtering device for application in this method, and a cartridge for use in such a filtering device.

The invention relates to a method and an arrangement for operating a system in which dismantling works are performed underwater in a liquid-filled vessel (10) of a nuclear facility, the liquid being guided in a circuit (20) and flowing through at least one filter device (26, 28, 30). The liquid in the circuit flows through at least a first filter device (26) in the form of a coarse filter and a second filter device (28), in which at least one device from the group of ion exchangers (1, 2, 3), reverse osmosis systems, ultrafiltration systems, activated carbon filters, zeolite filters, and biological filters is used for filtration.

The invention relates to a method and an arrangement for operating a system in which dismantling works are performed underwater in a liquid-filled vessel (10) of a nuclear facility, the liquid being guided in a circuit (20) and flowing through at least one filter device (26, 28, 30). The liquid in the circuit flows through at least a first filter device (26) in the form of a coarse filter and a second filter device (28), in which at least one device from the group of ion exchangers (1, 2, 3), reverse osmosis systems, ultrafiltration systems, activated carbon filters, zeolite filters, and biological filters is used for filtration.

The invention relates to technology for processing liquid radioactive waste containing, inter alia, tritium isotopes, which are formed in various nuclear industry plants, and also during decommissioning of such plants. The technical result of the claimed invention consists in simplifying the technological procedure for processing liquid radioactive waste containing, inter alia, tritium isotopes by excluding complicated and lengthy operations associated with testing a concrete mixture produced from deactivated liquid radioactive waste, and also in increasing the ecological safety by reducing the size of areas for storage of the waste produced during the processing of the liquid radioactive waste. The claimed technical result is achieved in that a method for processing liquid radioactive waste containing, inter alia, tritium isotopes involves removing radioactive substances from the liquid radioactive waste so as to produce a low-level waste solution, and introducing a binder into the low-level waste solution produced in order to prepare a concrete mixture which complies with structural, radioecological, and sanitary and hygiene requirements, wherein components that have a negative effect on the technical characteristics of the concrete mixture being produced are removed from the low-level waste solution before the binder is added.