An object to be decontaminated contaminated with radioactive material is introduced into an acid eluting solvent to dissolve the radioactive material. The radioactive material dissolved is concentrated and separated from the eluting solvent in the present method. The object to be decontaminated comprises contaminated soil and contaminated liquid. One or both of the contaminated soil and the contaminated liquid are collected and introduced into the eluting solvent. The radioactive materials and the object to be decontaminated dissolved in the eluting solvent are separated into solid and liquid. The decontaminated soil separated from the eluting solvent is collected. The eluting solvent used for separating the radioactive material and in which radioactive material is dissolved is concentrated.

An object to be decontaminated contaminated with radioactive material is introduced into an acid eluting solvent to dissolve the radioactive material. The radioactive material dissolved is concentrated and separated from the eluting solvent in the present method. The object to be decontaminated comprises contaminated soil and contaminated liquid. One or both of the contaminated soil and the contaminated liquid are collected and introduced into the eluting solvent. The radioactive materials and the object to be decontaminated dissolved in the eluting solvent are separated into solid and liquid. The decontaminated soil separated from the eluting solvent is collected. The eluting solvent used for separating the radioactive material and in which radioactive material is dissolved is concentrated.

The present invention relates to a process for treating aqueous effluents from the primary circuit of a nuclear power plant implementing a separation of boric acid using a reverse osmosis membrane, characterized by the fact that it comprises steps consisting of treating the effluents using a multi-stage assembly composed of reverse osmosis modules comprising a membrane with a high boron rejection rate, arranged in parallel and in series, and recycling of the intermediate products to different points in the assembly.

The present invention relates to a process for treating aqueous effluents from the primary circuit of a nuclear power plant implementing a separation of boric acid using a reverse osmosis membrane, characterized by the fact that it comprises steps consisting of treating the effluents using a multi-stage assembly composed of reverse osmosis modules comprising a membrane with a high boron rejection rate, arranged in parallel and in series, and recycling of the intermediate products to different points in the assembly.

Methods and materials are described for the removal of iodate from aqueous solutions. The methods comprise reduction of the iodate to iodide and subsequent or concurrent removal of the iodide by sorption, ion exchange, or precipitation. These methods are effective for the removal of radioactive iodine from radioactive and nuclear wastes.

Methods and materials are described for the removal of iodate from aqueous solutions. The methods comprise reduction of the iodate to iodide and subsequent or concurrent removal of the iodide by sorption, ion exchange, or precipitation. These methods are effective for the removal of radioactive iodine from radioactive and nuclear wastes.

A method and apparatus for separation of particulates from liquids by filtration for the purpose of removal or recovery of the particulates. Reducing the surfaces forces associated with electrostatic attraction between the particles and the filter medium is accomplished by modifying or coating the surface of the filter medium with one or more materials that exhibit a surface charge closer to or the same as that of the particulates in a given aqueous liquid. This permits filtration by mechanical interception but reduces the subsequent adhesion that prevents or hinders regeneration. The method and apparatus can be used in the filtration of radioactive particulates and contaminants from aqueous liquid inventories or liquid process streams with radiation resistant filter medium such as ceramics, sintered metal powders, or sintered metal fibers. These types of filters can exhibit a surface charge very different from that of the particulates targeted for separation by mechanical filtration.

A method and apparatus for separation of particulates from liquids by filtration for the purpose of removal or recovery of the particulates. Reducing the surfaces forces associated with electrostatic attraction between the particles and the filter medium is accomplished by modifying or coating the surface of the filter medium with one or more materials that exhibit a surface charge closer to or the same as that of the particulates in a given aqueous liquid. This permits filtration by mechanical interception but reduces the subsequent adhesion that prevents or hinders regeneration. The method and apparatus can be used in the filtration of radioactive particulates and contaminants from aqueous liquid inventories or liquid process streams with radiation resistant filter medium such as ceramics, sintered metal powders, or sintered metal fibers. These types of filters can exhibit a surface charge very different from that of the particulates targeted for separation by mechanical filtration.

A decontamination method in which tritium radiation is attenuated or eliminated from radioactive contaminated water. In the decontamination method, the following steps are executed: a step for performing an addition treatment to add a prescribed amount of a mineral powder such as a silicon dioxide ore and a nano-level carbon liquid to heated tritium-contaminated water in an addition treatment tank; a step for pumping the addition-treated water from the addition treatment tank to a mineral solid filled tank using a hydraulic pump; a step for causing the addition-treated water to collide with a mineral solid and passing the addition-treated water through the mineral solid filled tank; a step for returning the passed water to the addition treatment tank using the hydraulic pump; and a circulation process step for repeating the aforementioned steps in a prescribed period of time.

A separation apparatus for separating a supply of high-level nuclear waste (HLW), where the HL nuclear waste is separated into high-mass and low-mass portions. The high-and-low mass portions of the HLW have respective atomic masses that are above and below an atomic mass cut-off point of the separation apparatus. The separation apparatus includes first and second ICP torches that are respectively mounted to and within an apparatus housing. The apparatus housing defines a cylindrical separation chamber and includes first and second magnetic elements which generate a magnetic field along the length of the separation chamber, and a plurality concentric ring electrodes which generate an electric field that is perpendicular to, and which crosses the magnetic field. The supply of HLW is subject to a mass separation process within the separation chamber using the set of crossed electric and magnetic fields.