A system and method for consolidating used nuclear fuel rods using tools operably suspendable in a recess containing the used nuclear fuel rods. The systems and methods safely consolidate the used nuclear fuel rods in containers.

The present invention relates to a remote dismantling system for a nuclear power plant. The remote dismantling system comprises: a transfer system for transferring an object to be cut, the object being placed on one side of the transfer system; and a parallel vertical rail robot arm system arranged within the movement radius of the transfer system and comprising a cutting robot arm for cutting the object to be cut. The transfer system comprises a gantry crane and a jib crane which are arranged to be movable across each other and transfer the object to be cut. The parallel vertical rail robot arm system comprises a transfer robot arm arranged to be vertically movable along with the cutting robot arm in order to transfer finely cut pieces which have been cut from the object to be cut.

The present disclosure relates to a method of removing a radioactive structure from a nuclear power plant. The method includes flattening at least a portion of an outer surface of a drilling portion of a wall of a nuclear reactor vessel when the portion of the outer surface is uneven, wherein the radioactive structure is buried in the wall and the drilling portion is adjacent to the radioactive structure, installing a drilling device in the flattened drilling portion and performing a drilling operation, extracting the radioactive structure from the wall, and cutting the extracted radioactive structure and storing pieces of the cut radioactive structure in a shielding container.

The invention proposes a tool and device, with the aid of which it is possible to remove the surface of walls, ceilings and floors also in the corners of contaminated interiors.

A wire saw apparatus comprises: a first pulley system from which a wire is withdrawn toward a structure to be cut; a second pulley system into which the wire is introduced from the structure; a first dust collection pipe unit provided to surround the wire between an end part at which surrounding of the structure by the wire ends and a part at which the wire is introduced into the first pulley system; and a second dust collection pipe unit provided to surround the wire between a start part at which surrounding of the structure by the wire starts and a part at which the wire is withdrawn from the second pulley system.

A waste liquid treatment facility according to an exemplary embodiment of the present invention includes: a filter connected to a system of a nuclear power plant; a demineralizer connected to the filter; a reactor connected to the demineralizer and including a first lamp and a second lamp of different wavelengths connected in succession; a buffer tank connected to the filter, demineralizer, and reactor; and a circulation pipe portion connecting the filter, demineralizer, reactor, and buffer tank to form a circulation structure of a solution together with the system, wherein the solution sequentially passes through the first lamp and the second lamp.

A method for collection of dry samples taken directly from a nuclear reactor core interior. Incremental samples of irradiated metal alloy components of the reactor core may be taken and collected in-situ using a specialized metal-cutting drill bit having a hollow tungsten carbide sampling cutting head, in conjunction with an angled sampling gantry. The drill bit body has an interior airflow passage in hermetic communication with a filter located in a glove box. Air holes are formed through a face of the cutting head. A vacuumed airflow through the airflow passage and at the cutting head causes a sample of any of metal chips, filings, and dust to be obtained directly from the reactor core by being pulled through the air holes and into the airflow passage and ultimately into the filter. A collected sample may be analyzed for radionuclides and radioactivity level.

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.

A method for decommissioning a nuclear facility includes: floating the nuclear reactor pressure vessel above the cavity; rotating the reactor pressure vessel so that the upper portion of the nuclear reactor pressure vessel is closer to the bio-protective concrete than the lower portion; mounting the upper portion of the nuclear reactor pressure vessel on the neighboring upper surface of the bio-protective concrete; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the neighboring upper surface.

The present invention relates to a simulation of a nuclear facility dismantling operation, comprising: a database which includes information on at least one task constituting a nuclear facility dismantling operation and information on a virtual space related to the simulation of the dismantling operation; a plurality of head mounted displays (HMDs) which receives inputs of users related to the simulation; a simulation unit which generates the virtual space, transmits to the plurality of HMDs, the image of the virtual space including operator objects corresponding to each of the users of the plurality of HMDs, and processes the simulation of the dismantling operation according to the inputs received from each HMD user, wherein, when simulations which are different in at least one of the number of the users and the progress order of the tasks are processed, the simulation unit compares the simulations on the basis of at least one of the number of the users or the progress order of the tasks and displays a comparison result.