A method for treatment of spent ion-exchange resins for disposal includes feeding a mixture of spent ion-exchange resins to the a loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the a drying chamber, vacuum drying the ion-exchange resins and subjecting the resins to additional heat treatment in a high-temperature furnace, and unloading the treated ion-exchange resins into a transport container. A device for treatment of spent ion-exchange resins includes a loading tank, a metering device connected to a drying chamber, an inclined feed screw located between the loading tank and the metering device, a vacuum pump, a heated gas filter, a high-temperature furnace equipped with a vacuum drying and gas purification system, and a feeding device located between the drying chamber and the high-temperature furnace. A docking unit is connected to a lower part of the high-temperature furnace.

Systems and methods are disclosed for inspection, maintenance, debris removal, and cleaning of environments that may be difficult to access and hazardous. The system comprises a mast assembly, an arm assembly, a debris removal system, and a drive system. The mast assembly comprises an inner mast and an outer mast having a central axis about which the arm assembly revolves. The arm assembly provides support for the debris removal system. The debris removal system comprises a bucket tool, a plow tool, and one or more hoses for clearing and removing debris. The drive system comprises a plurality of one or more of cables, pulleys, rollers, and hoists to at least one of control motion of the arm assembly, raise and lower the inner mast, and position and control at least one of the bucket tool and the plow tool. The system is at least one of manually or automatically controlled.

Systems and methods are disclosed for inspection, maintenance, debris removal, and cleaning of environments that may be difficult to access and hazardous. The system comprises a mast assembly, an arm assembly, a debris removal system, and a drive system. The mast assembly comprises an inner mast and an outer mast having a central axis about which the arm assembly revolves. The arm assembly provides support for the debris removal system. The debris removal system comprises a bucket tool, a plow tool, and one or more hoses for clearing and removing debris. The drive system comprises a plurality of one or more of cables, pulleys, rollers, and hoists to at least one of control motion of the arm assembly, raise and lower the inner mast, and position and control at least one of the bucket tool and the plow tool. The system is at least one of manually or automatically controlled.

A container system for radioactive waste and method for using the same is provided. The system includes a canister configured for holding radioactive waste and a lid system. In one embodiment, the lid system comprises a two-part lid assembly including a confinement lid and a shielded lifting lid. The confinement lid is detachably mounted to the confinement lid. In use, the lifting lid supports the confinement lid for lifting and placement on the canister. The lifting lid further shields operators while the confinement lid is mounted to the canister. Thereafter, the lifting lid is removed and may be reused for confinement lid mountings on other canisters. In one embodiment, the confinement lid is bolted to the canister. The canister may be disposed in a protective overpack for transport and storage.

A container system for radioactive waste and method for using the same is provided. The system includes a canister configured for holding radioactive waste and a lid system. In one embodiment, the lid system comprises a two-part lid assembly including a confinement lid and a shielded lifting lid. The confinement lid is detachably mounted to the confinement lid. In use, the lifting lid supports the confinement lid for lifting and placement on the canister. The lifting lid further shields operators while the confinement lid is mounted to the canister. Thereafter, the lifting lid is removed and may be reused for confinement lid mountings on other canisters. In one embodiment, the confinement lid is bolted to the canister. The canister may be disposed in a protective overpack for transport and storage.

Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

A hazardous material storage system includes a drillhole extending into the Earth and including an entry at least proximate a terranean surface. The drillhole includes a substantially vertical portion, a curved portion, and a horizontal portion that includes a hazardous waste repository formed within a first portion of the horizontal portion of the drillhole, the hazardous waste repository vertically isolated, by a rock formation, from a subterranean zone that includes mobile water, and a safety runway formed within a second portion of the horizontal portion exclusive of the hazardous waste repository and adjacent the curved portion, the safety runway defined by a particular length.

A hazardous material storage system includes a drillhole extending into the Earth and including an entry at least proximate a terranean surface. The drillhole includes a substantially vertical portion, a curved portion, and a horizontal portion that includes a hazardous waste repository formed within a first portion of the horizontal portion of the drillhole, the hazardous waste repository vertically isolated, by a rock formation, from a subterranean zone that includes mobile water, and a safety runway formed within a second portion of the horizontal portion exclusive of the hazardous waste repository and adjacent the curved portion, the safety runway defined by a particular length.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.