The present disclosure provides an application of a titanium carbide/porous carbon composite in electrochemical treatment of uranium-containing wastewater, and belongs to the technical field of wastewater treatment. The present disclosure provides the application of the titanium carbide/porous carbon composite in electrochemical treatment of uranium-containing wastewater. Titanium carbide (TiC) is a typical transition metal carbide and has good conductivity and excellent chemical stability; compared with a titanium dioxide/carbon nanomaterial, the titanium carbide/porous carbon composite has a rich pore structure that provides a large number of activated adsorption sites for adsorption of metal ions during electro-adsorption, so that the electro-adsorption efficiency can be substantially improved, and a better electro-adsorption effect is obtained.

Novel iron-phosphate nanoparticles have been synthesized here. These are less than 12 nanometers in dimension. They are deemed useful for remediation of heavy metals and radionuclides and can be applied to insitu remediation of contaminated soils and contaminated waters.

Provided is a hydrogen isotope adsorbent with differential binding properties and including mesoporous silica doped with fluorine.

Provided are a biomineralogical method for removing cesium ions. The method for removing cesium ions, the method comprising: adding metal-reducing bacteria, an iron source, and a sulfur source into a solution containing the cesium ions to convert the cesium ions into a solid mineral incorporating cesium. The method for removing cesium ions according to the present invention has advantages in that the cesium ions may be removed with high efficiency and small volume even in the case in which competing ions are present at a high concentration like sea water.

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.

Metal-chelating compositions having the structure (1a) wherein: R.sup.1, R.sup.2, R.sup.3, and R.sup.4 are independently selected from the following groups: (i) hydrogen atom, (ii) hydrocarbon groups (R) containing 1-12 carbon atoms; (iii) halogen atoms; (iv) —P(R.sup.5) (═O)OH groups; (v) —C(═O)OH groups; (vi) —S(═O).sub.2OH groups; and (vii) —OH groups, wherein R.sup.5 is selected from hydrocarbon groups (R) and —OH; R.sup.1 and R.sup.2 may optionally interconnect to form Ring A fused to the ring on which R.sup.1 and R.sup.2 are present; R.sup.3 and R.sup.4 may optionally interconnect to form Ring B fused to the ring on which R.sup.3 and R.sup.4 are present; wherein Ring A and Ring B are optionally and independently substituted with one or more of groups (ii)-(vii). Methods of using the above-described compositions for chelating metal ions having an atomic number of at least 56 (e.g., Ba or Ra) are also described. ##STR00001##

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 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.

The present invention discloses a method for the separation of radionuclides from an aqueous radioactive waste solution, the method comprising: receiving of an aqueous radioactive waste solution, adding at least one zirconium salt to the aqueous radioactive waste solution, changing the pH of the radioactive waste solution to obtain a precipitate P, and separating the precipitate P from the radioactive waste solution. The present invention also discloses the use of zirconium salts, preferably zirconium oxychloride, zirconium nitrate or a zirconium oxynitrate or any mixture thereof, for the treatment of aqueous radioactive waste solution, preferably acidic or alkaline intermediate or low level radioactive waste solution, preferably an acidic intermediate and/or low level radioactive waste solution.