An exposure prevention device for dismantling a heavy water reactor facility according to an embodiment includes: a shielding film that covers a front surface and a rear surface of a heavy water facility including a calandria and a calandria vault that accommodates the calandria; a plurality of radiation measuring instruments installed in the shielding film; and a motion detector installed in the shielding film.

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.

The present disclosure relates to a method of removing a nuclear power plant activation structure. Specifically, an embodiment of the present disclosure may provide a method of removing a nuclear power plant activation structure including flattening at least a portion of a wall surface of a peripheral portion of a wall of a nuclear reactor, the wall including a buried portion in which a nuclear power plant activation structure is buried and the peripheral portion circumferentially surrounding the buried portion; installing a drilling device in the flattened peripheral portion and performing a drilling operation; removing the nuclear power plant activation structure from the buried portion; and cutting the removed nuclear power plant activation structure and storing pieces of the cut nuclear power plant activation structure in a shielding container.

An apparatus for decommissioning heavy-water reactor facilities includes a shielding device including a drawing-out space that is mounted on the reactivity mechanism deck and communicates with one through-hole among the plurality of through-holes, a separating device that is inserted into the inside of one of the plurality of guide tubes through the drawing-out space and the one through-hole and cuts an end portion of the one guide tube connected to the calandria, and a drawing-out device that is inserted into the inside of the one guide tube through the drawing-out space and the one through-hole and supports the end portion of the one guide tube to draw out the one guide tube into the inside of the drawing-out space through the one through-hole.

An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

A nuclear reactor dismantlement system according to an embodiment includes bio-protective concrete including a first space into which a reactor is inserted and a second space that is connected to the first space and is expanded in the first space, a moving device that is positioned in the second space and moves the reactor, and a cutting device that is positioned in the second space and cuts the reactor.

A nuclear dismantling system for dismantling equipment contaminated with radioactive contamination, including a dismantling apparatus to be operated remotely while in a nuclear facility and a control system communicatively coupled to the dismantling apparatus to control the dismantling apparatus remotely.

Disclosed herein is a machine for cutting nozzles of reactor vessels. The machine for cutting nozzles of reactor vessels comprises a cutting unit positioned at an upper surface edge of a reactor vessel having a nozzle and having a saw blade part having different contact areas to cut the nozzle, a drive unit providing the saw blade part with rotary power, and a foreign substance suction unit provided at one end of the cutting unit in contiguity with the saw blade part to suck foreign substances generated when the nozzle is cut by the saw blade part, wherein the foreign substance suction unit sucks the foreign substances by approaching an outer peripheral surface of the nozzle when the saw blade part moves in a cutting direction of the nozzle.

An apparatus for volume reduction of material removed from a hazardous environment. The apparatus includes a shielded housing for receiving a workpiece therein, at least one cutting unit having a cutting head operable for contactless cutting, and a drive unit for rotating the at least one cutting unit around a main axis so the cutting head cuts the workpiece.

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.