Systems and methods for capturing waste are disclosed. The systems and methods provide for a high level of confinement and long term stability. The systems and methods include adsorbing waste into a metal-organic framework (MOF), and applying pressure to the MOF material's framework to crystallize or make amorphous the MOF material thereby changing the MOF's pore structure and sorption characteristics without collapsing the MOF framework.

A method for storing nuclear fuel includes transferring a fuel assembly from a long term storage vault to a nuclear reactor core, removing the fuel assembly from the nuclear reactor core, determining a heat generation rate of the irradiated fuel assembly, and transferring the irradiated fuel assembly to one of an interim storage vault and a long term storage vault based on the determined heat generation rate.

The present invention discloses a waste liquid recovery system for a large storage tank, and relates to the technical field of retirements of radioactive storage tanks. The present invention includes a control terminal, a transition tank, a water storage tank, a water-ring vacuum pump, a water mist separator, a high-pressure water spray apparatus, a solid waste collecting and weighing apparatus, and a sewage pump, where the transition tank and storage tank is connected with two ends of a recovery pipeline respectively; the water storage tank is provided with a ventilation valve, a solid-liquid separator, and a rotary stirring apparatus; the transition tank is connected to an inlet port of the solid-liquid separator; and a waste water outlet port of the water storage tank is connected with the sewage pump. According to the present invention, solid-liquid separation, a simple structure and a high automation degree are achieved.

A method for retrofitting a nuclear power plant which include dismantling and removing all the components of the primary circuit apart from the LWR reactor vessel, which is essentially emptied of all material and neutralized, subsequently replacing a part of these components with subassemblies that are each made up of an integrated SMR reactor and a mixed concrete/metal structure, which mixed concrete/metal structure is also used as a reactor pit for the SMR reactor, which reactor pit is advantageously filled with water, anchoring the SMR to the inside of the reactor building and advantageously contributing to the third confinement barrier while ensuring minimal disruption to the infrastructure of the reactor building.

A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

The present invention discloses a waste liquid recovery system for a large storage tank, and relates to the technical field of retirements of radioactive storage tanks. The present invention includes a control terminal, a transition tank, a water storage tank, a water-ring vacuum pump, a water mist separator, a high-pressure water spray apparatus, a solid waste collecting and weighing apparatus, and a sewage pump, where the transition tank and storage tank is connected with two ends of a recovery pipeline respectively; the water storage tank is provided with a ventilation valve, a solid-liquid separator, and a rotary stirring apparatus; the transition tank is connected to an inlet port of the solid-liquid separator; and a waste water outlet port of the water storage tank is connected with the sewage pump. According to the present invention, solid-liquid separation, a simple structure and a high automation degree are achieved.

A dismantling and decontamination system of bioprotective concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under bioprotective concrete to form a lower penetrated part of the bioprotective concrete; a decontamination device inserted inside the bioprotective concrete for decontaminating radioactive waste of the inner wall of the bioprotective concrete; a waste receiving device movable through the lower penetrated part of the bioprotective concrete; and a blocking device for blocking the upper opening of the bioprotective concrete to block an outflow of the radioactive dust.

A method comprising: 1) positioning an inflatable pipe plug inside a high-vacuum beam line assembly proximate an axial gap between two beam tubes mechanically connected by a bellows-encased radio frequency (RF) shield; 2) inflating a balloon of the pipe plug proximate the axial gap to exert a uniform pressure along dislocated fingers of the RF shield; 3) angularly bending the bellows to enlarge a repair portion of the axial gap to a width larger than the dislocated finger(s); and 4) returning the dislocated finger(s) to the operation-ready RF shield position under the uniform pressure before 5) deflating and removing the inflatable pipe plug. A corrector system kit may comprise a set of custom-sized balloon(s) of a nitrile material type, a fixed-length or tailorable delivery hose, and a connector(s). A fluid (e.g., gas, liquid) pump delivers pressured fluid to the selected/tailored connector, through the delivery hose, and into the balloon.

A decontamination apparatus for decontaminating an external surface is provided. The decontamination apparatus has a moveable platform and a containment structure mounted on the moveable platform. The containment structure has at least one aperture and a respective contact surface arranged around the perimeter of the aperture. The contact surface is arranged to make contact with the external surface to define a working volume, when the containment structure is positioned proximal to the external surface. The decontamination apparatus includes a decontamination device arranged to decontaminate the external surface. The decontamination device is arranged within the working volume and arranged to access the external surface through the at least one aperture. There is also a vacuum system for generating a partial vacuum in the containment structure to apply a suction force to the external surface.