G21F9/16

METHOD FOR CONDITIONING AN ACID WASTE BY CEMENTATION
20220048824 · 2022-02-17 ·

A method for conditioning an acid waste by cementation, wherein the acid waste is chosen among liquids having a pH of no more than 4, semi-liquids having a pH of no more than 4, solids of which the partial or full dissolution in water leads to a solution or suspension having a pH of no more than 4, and mixtures thereof, which method comprises the steps of: a) preparing a cement paste having as components at least: a magnesium phosphate cement and the acid waste, and b) hardening the cement paste thus obtained, and is characterised in that in step a), the cement paste is prepared without subjecting beforehand the acid waste to any treatment consisting in reducing the acidity thereof.

Polymer composition
09757603 · 2017-09-12 · ·

This invention relates to a polymer composition, comprising: water; a water-soluble polymer; and solid particulates of a sequestering agent. The composition may be used for decontaminating, cleaning and/or washing substrates contaminated with contaminants and/or contaminated materials.

Polymer composition
09757603 · 2017-09-12 · ·

This invention relates to a polymer composition, comprising: water; a water-soluble polymer; and solid particulates of a sequestering agent. The composition may be used for decontaminating, cleaning and/or washing substrates contaminated with contaminants and/or contaminated materials.

RADIUM ADSORBENT COMPOSITIONS, SYSTEMS, AND METHODS OF USING THE SAME
20250232888 · 2025-07-17 ·

Radioactive material adsorbing clay material effectively and efficiently removes radioactive material, namely radium, from aqueous fluids, thereby purifying the same. Methods of synthesizing and using the same are further provided.

Solidifying-agent composition containing alumina cement for solidifying radioactive waste and method for solidifying radioactive waste using same

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

Solidifying-agent composition containing alumina cement for solidifying radioactive waste and method for solidifying radioactive waste using same

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

Integrated ion-exchange disposal and treatment system

A canister for interim storage and subsequent consolidation of waste materials via hot pressing and comprising at least one ion exchange material. The canister is configured to house the ion exchange material after it is exchanged with a contaminating ion without releasing the contaminating ion and to consolidate waste materials via hot-isostatic pressing. A method comprising contacting a fluid waste with an ion exchange material.

RECEPTOR AND METHOD FOR REMOVING OXOANIONS FROM AQUEOUS PHASE
20220169536 · 2022-06-02 ·

A receptor for the simultaneous removal of oxoanions and their counterions from aqueous phase, particularly containing radioactive wastes, containing amide groups specifically coordinating the oxoanions, as well as moieties specifically coordinating cations, according to the present invention is characterised in that it contains within one molecule domains binding oxoanions and domains binding cations, preferably adapting a molecular structure of a general formula: (I) wherein Z this is a group containing crown ether, preferably a benzocrown group, X is any substituent, including the Y-Z grouping, and Y is any substituent or 0 (i.e. a direct bond between N and Z), where the oxoanion binding domain is a squaramide unit coordinating the oxoanions through amide groups, and squaramide contains additional substituents that increase or decrease the acidity of its amide protons, compared to unsubstituted squaramide, whereas the counter ion binding domain is a crown ether of a size adjusted to the type of binding cation, which forms part of at least one of the aforementioned substituents of squaramide, where the receptor has the ability to remove oxoanions and their counterions from aqueous phase to another water-immiscible phase, preferably to organic phase, and has the ability to form soluble complexes in at least one of the aforementioned phases. The invention considers also a method of removing oxoanions in the form of inorganic salts from aqueous phase, using receptors of the invention in the form of organic molecules containing amide groups, according to the invention is characterised in that it uses the aforementioned receptors for simultaneous binding of oxoanions and their counterions in aqueous phase, preferably acidic when using the receptor with substituents increasing acidity of squaramide protons, or alkaline when using the receptor with substituents decreasing acidity of squaramide protons. A sensor for detecting oxoanions according to the invention is characterised in that it uses the aforementioned receptors, dissolved or suspended in an organic solvent or in a mixture of organic solvents, forming coloured complexes in contact with the phase containing given oxoanions. The preparation for removing oxoanions from aqueous solutions, particularly containing radioactive waste at the stage preceding their disposal by vitrification, is characterised in that it contains the receptor according to the invention, dissolved or suspended in the water-immiscible phase, and the appropriate amount of counterion facilitating extraction. A process of utilisation of aqueous solutions by vitrification, particularly solutions containing radioactive waste, is characte

Deep human-made cavern construction
11339611 · 2022-05-24 ·

Systems and/or methods of waste disposal use human-made caverns that are constructed within deep geological formations. A given human-made cavern may be constructed by first drilling out a vertical wellbore to a deep geological formation. Then a bottom portion of the vertical wellbore is jet drilled using an abrasive jetting fluid to form a launch chamber of void volume, that is sized to fit a reaming tool in its deployed open configuration. A reaming tool, in a closed configuration, is then inserted into the vertical wellbore for landing in the launch chamber. The reaming tool is then deployed into its open configuration while in the launch chamber. Reaming operations then occur from the launch chamber directed downwards within the deep geological formation, forming a given human-made cavern. The newly formed human-made cavern may be conditioned and/or configured for receiving amounts of the waste for long-term disposal and/or storage.

Method and device for disposing nuclear waste using deep geological repository

A disposal device comprises a raw material conveyor, a raw material mixer, a liquid waste conveying pipeline, an additive tank, a powder waste conveyor, an output pump, a liquid supply pump, a liquid supply manifold, an output manifold, a mixed liquid conveying pipeline, a high-pressure injection pump, a high-pressure pipeline, and a wellhead sealing device. A method of employing the device includes: drilling a well; forming a fracture in the granite stratum; preparing a raw material; and injecting, by using the disposal device, a sand-carrying feed liquid from a high-pressure injection pump into the fracture of the underground granite stratum, so as to perform solidification.