A method and plant for wet-route oxidation treatment of hazardous organic waste products, notably radioactive wastes, which may contain mineral fillers, the waste products being treated in a secure environment. The plant comprises a closed space, with a mechanism for bringing a volume of hazardous organic waste products containing mineral fillers, adding a given quantity of water mixed with a base to the predetermined volume in order to adjust the pH to a determined value so as to make a solution and/or a liquid suspension, with a pressure reactor and with mechanism for transferring the solution and/or liquid suspension into the pressure reactor, and a device for introducing an oxygen atmosphere into the pressure reactor and for pressurizing the atmosphere. A heating mechanism is provided for subjecting the contents of the pressure reactor to heat treatment at a temperature between 150 and 350 C. to complete the wet-route oxidation.

The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof. This system includes a wastewater collection unit; a pretreatment unit; a deep purification unit; a solid decay unit; a buffer unit; an online monitoring unit; and a control unit, wherein the online monitoring unit includes a radioactivity level detection module for detecting total and total radioactivity concentrations of inlet and outlet water of a medium in each unit, and a real-time monitoring module for treatment process parameters. The present disclosure discloses an integrated rapid treatment system for nuclear medical radioactive wastewater and an application method thereof, which can efficiently and quickly purify multi-nuclide organic low-level wastewater produced by a nuclear medical process, and realize rapid online monitoring and automatic control at the same time.

A hazardous material storage bank includes a wellbore extending into the Earth and including an entry at least proximate a terranean surface, the wellbore including a substantially vertical portion, a transition portion, and a substantially horizontal portion; a storage area coupled to the substantially horizontal portion of the well bore, the storage area within or below a shale formation, the storage area vertically isolated, by the shale formation, from a subterranean zone that includes mobile water; a storage container positioned in the storage area, the storage container sized to fit from the wellbore entry through the substantially vertical, the transition, and the substantially horizontal portions of the wellbore, and into the storage area, the storage container including an inner cavity sized enclose hazardous material; and a seal positioned in the wellbore, the seal isolating the storage portion of the wellbore from the entry of the wellbore.

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.

A method of treating a liquid borate waste includes the following steps: modulating a raw liquid borate waste; concentrating the liquid borate waste to make a high-concentration liquid polyborate waste; performing granulation of the high-concentration liquid polyborate waste with a granulating agent and preparing solid borate granules; and making the solid borate granules into a monolithic waste form with good performance.

Open pit mine (OPM) structures are modified or built new for use in disposing of low-level radioactive/nuclear waste (LLW). A drainage system is added to the OPM to drain water, such as, but not limited to, rain water, out of a volume of the OPM and to a particular geologic zone located far below the OPM that is isolated away from the local water table. Cells are formed within the volume of the OPM that are configured to receive the LLW. Cells are added to the OPM from a bottom towards a top of the OPM. Void spaces around the LLW materials within the cells are filled in with a protective-medium to mitigate against radionuclide migration away from the LLW materials within the cells. The protective-medium may be a blend of carbon nanotubes and a foam cement slurry. The carbon nanotubes may be made from reacting ethylene with vermiculite.

A liquid waste removal system for removing liquid waste remaining within a concrete drum that houses a container filled with concentrated waste liquid is disclosed. A liquid waste removal system according to an embodiment of the present invention, which is for removing liquid waste remaining inside a concrete drum that houses a container filled with radioactive waste, includes: a fixed support supporting and fixing the concrete drum; and a transfer pipe penetrating one side of the concrete drum and discharging the liquid waste out of the concrete drum.

The present invention relates to a method solidifying radioactive waste containing boron, The method includes (a) mixing the radioactive waste, metakaolin, fumed silica, potassium hydroxide, and water to generate a second mixture, in which the radioactive waste contains boron.