Patent classifications
G21F9/167
Immobilization of organic radioactive and non-radioactive liquid waste in a composite matrix
A method for immobilizing liquid radioactive waste is provided, the method having the steps of mixing waste with polymer to form a non-liquid waste; contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to cause the polymer, waste, and filler to irreversibly bind in a solid phase, and compressing the solid phase into a monolith. The invention also provides a method for immobilizing liquid radioactive waste containing tritium, the method having the steps of mixing liquid waste with polymer to convert the liquid waste to a non-liquid waste, contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to form homogeneous, chemically stable solid phase, and compressing the chemically stable solid phase into a final waste form, wherein the polymer comprises approximately a 9:1 weight ratio mixture of styrene block co-polymers and cross linked co-polymers of acrylamides.
IMMOBILIZATION OF ORGANIC RADIOACTIVE AND NON-RADIOACTIVE LIQUID WASTE IN A COMPOSITE MATRIX
A method for immobilizing liquid radioactive waste is provided, the method having the steps of mixing waste with polymer to form a non-liquid waste; contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to cause the polymer, waste, and filler to irreversibly bind in a solid phase, and compressing the solid phase into a monolith. The invention also provides a method for immobilizing liquid radioactive waste containing tritium, the method having the steps of mixing liquid waste with polymer to convert the liquid waste to a non-liquid waste, contacting the non-liquid waste with a solidifying agent to create a mixture, heating the mixture to form homogeneous, chemically stable solid phase, and compressing the chemically stable solid phase into a final waste form, wherein the polymer comprises approximately a 9:1 weight ratio mixture of styrene block co-polymers and cross linked co-polymers of acrylamides.
Metal-organic framework templated synthesis of porous inorganic materials as novel sorbents
A novel metal-organic framework (MOF) templated process for the synthesis of highly porous inorganic sorbents for removing radionuclides, actinides, and heavy metals is disclosed. The highly porous nature of the MOFs leads to highly porous inorganic sorbents (such as oxides, phosphates, sulfides, etc) with accessible surface binding sites that are suitable for removing radionuclides from high level nuclear wastes, extracting uranium from acid mine drainage and seawater, and sequestering heavy metals from waste streams. In some cases, MOFs can be directly used for removing these metal ions as MOFs are converted to highly porous inorganic sorbents in situ.
Method for removing radioactive cesium, hydrophilic resin composition for removal of radioactive cesium, method for removing radioactive iodine and radioactive cesium, and hydrophilic resin composition for removal of radioactive iodine and radioactive cesium
A method for removing radioactive cesium and/or iodine from a radioactive substance in liquid and/or a solid matter using a hydrophilic resin composition comprising a hydrophilic resin and a metal ferrocyanide compound, wherein the hydrophilic resin includes at least one hydrophilic resin selected from the group consisting of a hydrophilic polyurethane resin, a hydrophilic polyurea resin, and a hydrophilic polyurethane-polyurea resin each having at least a hydrophilic segment, and a metal ferrocyanide compound is dispersed in the hydrophilic resin composition in a ratio of at least 1 to 200 mass parts relative to 100 mass parts of the hydrophilic resin.
RADIOACTIVE WASTE IMMOBILIZATION APPARATUS AND IMMOBILIZATION METHOD USING THE SAME
A radioactive waste immobilization apparatus for immobilizing radioactive waste loaded in a high-integrity container to enhance the storage safety of the radioactive waste and a radioactive waste immobilization method using the same are disclosed. A radioactive waste immobilization apparatus according to an embodiment of the present invention, which is for immobilizing the upper part of radioactive waste loaded in a high-integrity container to prevent the possibility of the radioactive waste leaking to the outside, includes: a polymer resin injection unit forming a polymer resin layer by injecting an immobilizing polymer resin onto the radioactive waste loaded in the high-integrity container; a polymer resin sensing unit adjusting an injection amount of the polymer resin by measuring a thickness of the polymer resin layer; and a light curing unit curing the polymer resin layer.