A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a ventilated system for storing high level waste emitting heat, the system comprising: an air-intake shell forming an air-intake cavity; a plurality of storage shells, each storage shell forming a storage cavity; a lid positioned atop each of the storage shells; an outlet vent forming a passageway between an ambient environment and a top portion of each of the storage cavities; and a network of pipes forming hermetically sealed passageways between a bottom portion of the air-intake cavity and at least two different openings at a bottom portion of each of the storage cavities such that blockage of a first one of the openings does not prohibit air from flowing from the air-intake cavity into the storage cavity via a second one of the openings.

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

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 and 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 and automatically controlled.

Methods for storing or disposing of nuclear waste include forming a drillhole that extends into the Earth from a terranean surface. The drillhole includes an entry at least proximate the terranean surface, a substantially vertical drillhole portion, and a hazardous material storage drillhole portion that is coupled to the substantially vertical drillhole portion and is formed in a subterranean salt formation. The methods further include moving a storage canister into the hazardous material storage drillhole portion. The storage canister is sized to fit from the drillhole entry through the substantially vertical drillhole portion, and into the hazardous material storage drillhole portion of the drillhole. The storage canister has an inner cavity that encloses nuclear waste material. The methods further include positioning a seal in the drillhole to isolate the hazardous material storage drillhole portion of the drillhole from the entry of the drillhole.

Methods for storing or disposing of nuclear waste include forming a drillhole that extends into the Earth from a terranean surface. The drillhole includes an entry at least proximate the terranean surface, a substantially vertical drillhole portion, and a hazardous material storage drillhole portion that is coupled to the substantially vertical drillhole portion and is formed in a subterranean salt formation. The methods further include moving a storage canister into the hazardous material storage drillhole portion. The storage canister is sized to fit from the drillhole entry through the substantially vertical drillhole portion, and into the hazardous material storage drillhole portion of the drillhole. The storage canister has an inner cavity that encloses nuclear waste material. The methods further include positioning a seal in the drillhole to isolate the hazardous material storage drillhole portion of the drillhole from the entry of the drillhole.

The invention relates to an apparatus for treating waste material including organic components and radioactive agents. In the apparatus the waste material including organic components and radioactive agents are gasified at temperature between 600-950° C. in a fluidized bed reactor to form a gaseous material. The gaseous material is than cooled in a water quenching device so that temperature is between 300-500° C. after the cooling. The solid fraction including radioactive agents is removed from the gaseous material in a in at least one filtration device. A gas scrubbing device then removes sulphur by scrubbing the treated gaseous material after the filtration in order to form a treated gaseous material.

The invention relates to an apparatus for treating waste material including organic components and radioactive agents. In the apparatus the waste material including organic components and radioactive agents are gasified at temperature between 600-950° C. in a fluidized bed reactor to form a gaseous material. The gaseous material is than cooled in a water quenching device so that temperature is between 300-500° C. after the cooling. The solid fraction including radioactive agents is removed from the gaseous material in a in at least one filtration device. A gas scrubbing device then removes sulphur by scrubbing the treated gaseous material after the filtration in order to form a treated gaseous material.

The invention relates to a nuclear facility pool cleaning device having a floating platform, capable of floating in water, having buoyancy bodies; a drive device for displacing the floating platform on the surface of a water-filled nuclear facility pool to be cleaned; a winching device connected to the floating platform; a pump which is winchable vertically by the winching device and has a vacuum hose, connected thereto at its first end, for cleaning the bottom of the nuclear facility pool; a remote control device for remotely operating at least the drive device and the winching device; an optional stationary external storage tank; and wherein the second end of the vacuum hose preferably leads at least indirectly into the stationary external storage tank.