Apparatus for treating a source of radioactive emission, the apparatus including at least one reflecting means adapted to be in proximity to the source for receipt of the radioactive emission and to at least partially reflect received emission towards the source, thereby effecting reduction of the radioactive emission from the source.

The invention relates to the field of nuclear technology, in particular, to the disposal of spent long-length elements of a nuclear reactor. The invention reduces the complexity and time required to splice long-length elements and minimizes dose loads on attendants. The method of splicing long-length elements of a nuclear reactor into fragments involves placement of long-length elements inside the container and subsequent cutting. The long element is lowered into the container to its full height and cut on the level of the upper edge of the container with the separation from it of a fragment equal to the height of the container, then the upper part of the long-length element remaining after cutting is lowered inside the container to its full height and the cutting of the long-length element into fragments is repeated until it is fully spliced.

The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

A sparger includes a main pipe connecting inside and outside of a water tank having a storage space therein for storing cooling water, so as to define a flow path through which steam and air containing radioactive materials generated outside the water tank are discharged into the cooling water, a header part connected to one end portion of the main pipe located in the storage space, and having a storage chamber in which the steam and air transferred through the main pipe are collected, and a plurality of discharge nozzles disposed in a spacing manner, each having inlet and outlet formed on one end located in the storage chamber and another end located in the storage space, respectively, to discharge the steam and air from the storage chamber to the storage space, and at least some of the plurality of discharge nozzles protruding from the header part by different lengths.

The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

A furnace isolation chamber for containing a component to be Hot Isostatically Pressed is disclosed. The disclosed furnace includes inherent passive features to assist in the containment of released toxic gases via a thermal gradient within the chamber. The chamber comprises longitudinally cylindrical sidewalls; a top end extending between and permanently connected to the sidewalls, thereby closing one end of the chamber; and a movable bottom end, which is opposite the top end and forms a base end of the chamber. The movable bottom end is adapted to receive the component, and comprises a mechanism for raising and lowering the component into the high temperature zone of the furnace in the HIP system. The isolation chamber forms an integral part of the HIP system with the base end of the chamber comprising a cool zone as a result of being located outside of the high temperature zone of the furnace.

The invention is intended for integrated decontamination of soils contaminated with mercury (amalgam) or/and radionuclides. Method for soil decontamination includes preparation of pulp by mixing soils with water at the soil sampling point with separation of fraction with fragments more than 100 mm in the pulp preparation module, disintegration of pulp and soil aggregates in the disintegration module with separation of plants residues and fraction with fragments more than 10 mm. Pulp thickening. In the hydroclassification module the pulp is separated into sand and fine particle fractions, the fine particle fraction goes to the dehydration module, designed as a concentrator, where it is thickened and dehydrated for further disposal. If mercury and amalgam are present in soils they are separated in the thickening module. Technical resultimplementation of a low-waste nonchemical technology for decontamination of soil from mercury, its water-insoluble forms, amalgam or/and radionuclides in a single technological process without equipment resetting, separation of metal mercury or its amalgam.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

According to one aspect of the invention, a method to create a ceramic waste form from used nuclear fuel. An active metal salt waste, a rare earth metal waste, and raw materials are received. The active metal salt waste is combined with the rare earth metal waste, forming a waste salt. The waste salt is then heated to approximately 500 C. The raw materials are also heated to approximately 500 C. The waste salt and raw materials are then blended to form a homogenous waste mixture. The homogenous waste mixture is heated to a first predetermined temperature for a predetermined amount of time, creating a ceramic waste form. The ceramic waste form is cooled to a second predetermined temperature.

A method for decommissioning a heavy water reactor facility includes: removing the plurality of guide tubes from a plurality of through-holes; installing a plurality of shielding stoppers in the plurality of through-holes; removing the shielding stopper installed in one through-hole of the plurality of through-holes, and inserting a cutting device into a lower portion of the reactivity mechanism deck through the one through-hole to cut a connection portion between the reactivity mechanism deck and the calandria vault by using the cutting device; and separating the reactivity mechanism deck from the calandria vault.