Disclosed is a process method and system for upfront sampling and characterization to selectively and representatively sample for activation levels of nuclear reactor core irradiated metal alloy internal components using a specialized robust hard metal reactor bit hollow tungsten carbide sampling head in conjunction with bespoke angled sampling gantry. The invention relates to the field of a nuclear reactor metal alloy vacuum hollow sampling head, sampling gantry, and retrieval system. The nuclear-activated metal alloys are drilled and sampled using a TruProBit® metal cutting drill bit. The long hollow drill bit with a hollow metal sampling head traverses the nuclear reactor metal layers and void spaces to cut and retrieve only metal alloy samples. The dry vacuumed airflow picks up the discrete incremental sample of metal filings, chips, and dust produced by the hollow metal cutting edges of the sampling head into a filter and then analyzed for radionuclides of concern.

A method for complex-decommissioning a nuclear facility is disclosed. The method for complex-decommissioning the nuclear facility includes: cutting and expanding an inner wall of the cavity; installing a cutting device that cuts and decommissions the nuclear reactor pressure vessel inside the cavity; fixing the nuclear reactor pressure vessel inside the cavity by using a fixture; and cutting and decommissioning the nuclear reactor pressure vessel fixed inside the cavity by using a cutting device.

An underwater decommissioning method of a nuclear facility is disclosed. An underwater decommissioning method of a nuclear facility that includes a nuclear reactor pressure vessel and bio-protective concrete including a cavity in which the nuclear reactor pressure vessel is positioned, includes: (a) floating the nuclear reactor pressure vessel above the cavity; (b) forming an insertion part filled with water in a side spaced apart from the cavity, and installing a support part on a bottom surface of the insertion part; (c) mounting a lower portion of the nuclear reactor pressure vessel on the support part; and (d) repeatedly cutting and decommissioning the nuclear reactor pressure vessel mounted on the support part by using a cutting device in an underwater position.

A radioactive structure dismantling method of a heavy water reactor facility that includes a calandria including a main shell and a sub shell, a calandria vault that receives the calandria therein, and a cover assembly that covers the calandria according to an embodiment, includes: preparing dismantling of the calandria; dismantling a reactor pipe installed in the calandria; dismantling the cover assembly that covers the calandria; dismantling the calandria; and dismantling the calandria vault.

An exemplary embodiment of the present invention provides an apparatus for dismantling for heavy water reactor facilities, including: a cutting device configured to divide a calandria of the heavy water reactor facilities into a main shell and a sub-shell; and a transfer device configured to draw the main shell cut by the cutting device to the outside, wherein the transfer device includes a fixing unit configured to fix the calandria; and a transfer unit configured to transfer the fixing unit.

A device for capturing a shielding ball for a heavy water reactor according to an embodiment includes: a head for separating a shielding ball positioned inside an end shield of a calandria of a heavy water reactor to an outside; and a mover for moving the head to the end shield of the calandria, wherein the head includes a head body, an opening former installed on the head body and forming an opening in the end shield, and a gate installed on the head body and controlling an amount of movement of the shielding ball discharged to the outside through the opening.

A system for decommissioning a steam generator, comprising a structure defining a chamber for receiving the steam generator; and a mechanical assembly within the chamber for dismantling the steam generator.

A laser decontamination system according to an embodiment of the present invention includes: a laser generator generating a laser beam; an optical head inserted inside a pipe and focusing the laser beam on a contamination material inside the pipe for laser ablation; a first optical fiber connecting the laser generator and the optical head and transmitting the laser beam to the optical head; a spectroscope for analyzing a plasma spectrum generated in the pipe by the laser ablation; a second optical fiber connecting the spectroscope and the optical head and transmitting the plasma spectrum to the spectroscope; a dust collector for collecting a dust generated in the pipe by the laser ablation; a dust collection pipe connecting the dust collector and the inside of the pipe and transmitting the dust to the dust collector; and a blocking film positioned between the optical head and the pipe to block the dust.

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.

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.