The invention relates to an encapsulation composition for the storage or the confinement of waste which is toxic to health and/or the environment, comprising a resin composition containing at least one epoxy resin, and a hardening composition containing at least one polyamidoamine and at least one aromatic polyamine, said encapsulation composition having an aromaticity rate which is equal to, or higher than, 35%. The invention also relates to the use of said composition for encapsulating said waste.

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.

Proposed is a fines removal apparatus installed on a radioactive liquid waste granulator, the apparatus including: a body unit fastened to an outlet provided on the radioactive liquid waste granulator and configured to receive the granulated radioactive waste by an operation of a first opening/closing valve, the radioactive liquid waste granulator being configured to manufacture concentrated liquid waste and to manufacture granulated radioactive waste by drying the concentrated liquid waste. an air supply unit provided on one side of the body unit and configured to spray air to the supplied granulated radioactive waste at regular periods, thereby scattering and separating fines contained in the granulated radioactive waste; and a reprocessing unit provided in a vacuum state on an opposite side of the body unit and configured to allow the scattered fines to be transferred to the radioactive waste granulator along a transfer pipe by vacuum pressure.

The present invention is about a process for the treatment of radioactive liquid sewage, deriving from nuclear plants or hospital waste containing various metals, non-metals and organic compounds, in order to transform this sewage into a vitreous body safely retaining the nuclear elements or isotopes in a silica matrix; the invention also regards an apparatus for implementing the process in an automated way.

Provided are an adsorbent capable of removing radioactive water liquid including iodine compounds and/or antimony by means of a water passing treatment, and a method and an apparatus for treating radioactive waste liquid by using the adsorbent. The adsorbent includes a polymer resin and 10 parts by weight or more of a hydrous hydroxide of a rare earth element based on 100 parts by weight of the polymer resin, in which the hydrous hydroxide of the rare earth element has a water content of 1 part by weight to 30 parts by weight based on 100 parts by weight of a dry product thereof, and adsorbs iodine compounds and/or antimony.

The invention relates to an encapsulation composition for the storage or the confinement of waste which is toxic to health and/or the environment, comprising a resin composition containing at least one epoxy resin, and a hardening composition containing at least one polyamidoamine and at least one aromatic polyamine, said encapsulation composition having an aromaticity rate which is equal to, or higher than, 35%. The invention also relates to the use of said composition for encapsulating said waste.

There is disclosed a canister for interim storage and subsequent consolidation of waste materials via hot pressing. In an embodiment, the canister comprises at least one ion exchange material, and is configured to: house the ion exchange material after it is exchanged with a contaminating ion without releasing the contaminating ion; and consolidate via hot-isostatic pressing. There is also disclosed a contacting a fluid waste with an ion exchange material, wherein the ion exchange material is located in a canister; evacuating the canister; and hot isostatically pressing (HIP) the canister until it collapses under HIP conditions.

The present invention is a method for eliminating radioactive iodine using a hydrophilic resin that adsorbs radioactive iodine, wherein the hydrophilic resin is at least one selected from the group consisting of a hydrophilic polyurethane resin, a hydrophilic polyurea resin, and a hydrophilic polyurethane-polyurea resin and has a hydrophilic segment and, in the principal chain and/or a side chain in the structure thereof, has a tertiary amino group or has a tertiary amino group and polysiloxane segment. By means of the present invention, a novel method for eliminating radioactive iodine is provided that is simple and low-cost, furthermore does not require an energy source such as electricity, moreover can take in and stably immobilize the eliminated radioactive iodine within a solid, and is capable of reducing the volume of radioactive waste as necessary.

Provided are an adsorbent capable of removing radioactive water liquid including iodine compounds and/or antimony by means of a water passing treatment, and a method and an apparatus for treating radioactive waste liquid by using the adsorbent. The adsorbent includes a polymer resin and 10 parts by weight or more of a hydrous hydroxide of a rare earth element based on 100 parts by weight of the polymer resin, in which the hydrous hydroxide of the rare earth element has a water content of 1 part by weight to 30 parts by weight based on 100 parts by weight of a dry product thereof, and adsorbs iodine compounds and/or antimony.

The present invention is a method for eliminating radioactive iodine using a hydrophilic resin that adsorbs radioactive iodine, wherein the hydrophilic resin is at least one selected from the group consisting of a hydrophilic polyurethane resin, a hydrophilic polyurea resin, and a hydrophilic polyurethane-polyurea resin and has a hydrophilic segment and, in the principal chain and/or a side chain in the structure thereof, has a tertiary amino group or has a tertiary amino group and polysiloxane segment. By means of the present invention, a novel method for eliminating radioactive iodine is provided that is simple and low-cost, furthermore does not require an energy source such as electricity, moreover can take in and stably immobilize the eliminated radioactive iodine within a solid, and is capable of reducing the volume of radioactive waste as necessary.