Abstract: A nuclear power plant virtualization system and an operation method thereof are provided. A nuclear power plant virtualization system includes: virtual machine control parts; virtual machine network parts linked to the virtual machine control parts; and a virtualization platform switch linked with the virtual machine control parts and the virtual machine network parts, wherein the virtual machine control parts include a first MMI linked driver module, the virtual machine network parts include a second MMI linked driver module, and the virtual machine control parts and the virtual machine network parts modify an IP/MAC address in data communicated with the outside and allow the data communicated with the outside from the virtual machine control parts to pass through the virtual machine network parts, via the first MMI linked driver module and the second MMI linked driver module.

Abstract: The present invention relates to a method for detecting a void in a concrete composite member covered with a steel plate using a thermal image, and a method for managing the construction of a concrete composite member covered with a steel plate by applying same. According to the present invention, since the presence of the void is determined based on the steel plate surface temperature measured using the thermal image during the construction of the concrete composite member covered with the steel plate, the void generation may be precisely expected.

Abstract: The present invention relates to a system and method for monitoring the aging state of a power cable, in which a measuring unit measures the elongation at break of at least one power cable, a data generation unit generates a relational expression on the basis of the elongation at break of each of a heated cable, to which voltage has been applied to raise the temperature thereof, and a non-heated cable, to which no voltage has been applied, from among the measured cables, and an aging state derivation unit derives the aging state of a target power cable by calculating the elongation at break of the target power cable, of which the aging state is to be monitored, by using the relational expression. Accordingly, it is possible to verify the aging state of a power cable quickly and efficiently and to improve the credibility of the aging state of the power cable.

Abstract: There are provided a nuclear power plant dismantling method and apparatus. The nuclear power plant dismantling method includes: selecting a nuclear reactor to be dismantled; and performing nuclear power plant dismantling work on the nuclear reactor through a nuclear reactor dismantling apparatus, wherein the nuclear reactor dismantling apparatus includes: a frame unit shielding the nuclear reactor to prevent contaminants in the nuclear reactor from being released to the outside; a cutting module provided on the frame unit and performing cutting work on the nuclear reactor; a link fixing module having a hollow area formed therein, entering an internal space of the nuclear reactor to link the frame unit and the nuclear reactor with each other, and having a bar shape; and a purging module entering the hollow area of the link fixing module and performing purging on the inside of the nuclear reactor in order to secure safety in the cutting work.

Abstract: Provided are a remote restart system for vitrification equipment and a method of operating the same. The method of operating the remote restart system for the vitrification equipment includes: operating the vitrification equipment; and having power loss in the vitrification equipment, wherein the power loss occurs during or before operation of the vitrification equipment, the remote restart system assists in restarting the vitrification equipment when the power loss occurs in the vitrification equipment, and the remote restart system includes a low-temperature melting furnace, glass frit provided inside the low-temperature melting furnace, a titanium ring for heating the glass frit inside the low-temperature melting furnace, and a bar-shaped handling unit put into the low-temperature melting furnace to handle the glass frit to a state suitable for reignition of the glass frit.

Abstract: Provided is a method of treating radioactive waste glass fiber. The method of treating the radioactive waste glass fiber includes: preparing the radioactive waste glass fiber: loading the radioactive waste glass fiber into a canister; heat-treating the canister under set conditions through a heat treatment unit; and transferring the radioactive waste glass fiber whose volume has been reduced through the heat treatment.

Abstract: A small modular reactor apparatus and an operation method thereof are provided. A small modular reactor apparatus includes a body unit including a reactor core therein; and an opening and closing unit that is provided to be mounted and detachable from the body unit to open and close an interior of the body unit, wherein the opening and closing unit is provided to be mounted and detachable based on seating downward inside the body unit, and a plurality of In-core instrument (ICI) modules for state measurement of a small modular reactor are inserted and mounted in the opening and closing unit.

Abstract: A heavy-water reactor facility dismantling apparatus according to an embodiment includes: a first cutting device for cutting the periphery of a first nozzle portion of a calandria, wherein the first nozzle portion is connected to the upper end of a first pipe positioned in the calandria of a heavy-water reactor facility; a second cutting device for cutting a first support part of the calandria, wherein the first support portion is connected to the lower end of the first pipe connected to the first nozzle portion; and a fixing and drawing device for fixing and drawing the first nozzle portion cut by the first cutting device.

Abstract: A method for decommissioning a nuclear facility includes: floating a nuclear reactor pressure vessel above a cavity; positioning a mounting device on bio-protective concrete to cover the cavity with the mounting device; mounting a lower portion of the nuclear reactor pressure vessel on the mounting device; and cutting and decommissioning the nuclear reactor pressure vessel mounted on the mounting device.

Abstract: An artificial intelligence (AI) feedback system is provided.

Abstract: A safety cover structure of a nuclear facility is disclosed. The safety cover structure includes: a cover portion rotatably installed on a body protection concrete slab to cover a cavity where a reactor pressure container is located; a driving portion configured to rotate the cover portion relative to the cavity; an opening and closing portion that is installed on the cover portion and is configured to allow materials resulting from cutting and dismantling of the reactor pressure container to move therethrough; a fire extinguishing portion configured to extinguish a fire generated inside the cover portion; a dose sensor installed in the cover portion and configured to measure a radiation dose emitted from the reactor pressure container; and an alarm portion configured to receive a sensing signal from the dose sensor and provide an alarm when the measured radiation dose exceeds a predetermined value.

Abstract: A plasma torch has a torch body provided with a plurality of stacked torch body segments disposed between a rear electrode unit and a front electrode unit. The torch body forms a circular channel through which gas flows in an axial direction. Each torch body segment has a circular disc shape in which a central circular through-hole is formed to form the channel. Each segment includes gas supply ports defining a spiral-shaped flow path along the through hole on a first side of the segment so as to introduce a reactive gas, a cooling flow path, a cooling water supply flow path, a cooling water discharge flow path, a gas supply flow path, a gas branch flow path, a cooling water supply branch flow path, and a cooling water discharge branch flow path.

Abstract: The present invention provides a method for integrated online monitoring and a system for integrated online monitoring from a remote location for a nuclear power plant. The method includes a first step of collecting machine monitoring data of a plurality of units in the nuclear power plant selectively from the local data acquisition device via the monitoring data relay device, and a second step of collecting machine diagnostic data of a plurality of units in the nuclear power plant selectively from the local data acquisition device via the diagnostic data relay device.

Abstract: 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.

Abstract: 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.

Abstract: The present invention relates to a power plant early warning device and method which employ a multiple prediction model, and includes: a plurality of prediction models which receive information about the operation states of equipment in a power plant, and output prediction values and the reliabilities of the prediction values; a reliability analysis module which quantizes and analyzes the reliabilities output from the plurality of prediction models to determine the ranks of the plurality of prediction models, and calculates a final prediction value; a comparison module which compares the final prediction value with an actual measurement value, and outputs a residual; and a determination module which analyzes the residual to determine whether there are defects in the operating states of the equipment in the power plant.

Abstract: Provided is a UV reaction apparatus for treating waste liquid caused by system decontamination in a nuclear power plant. The UV reaction apparatus comprises a UV irradiation unit for irradiating UV light as a bar-shaped body; and a transit unit accommodating the UV irradiation unit therein, and for passing organic waste liquid to be irradiated with the UV light, wherein the transit unit comprises, an input unit, into which the organic waste liquid is input a discharge unit, through which the organic waste liquid is discharged, and an intermediate unit located between the input unit and the discharge unit, and in which the UV irradiation unit is located.

Abstract: Provided is a device for monitoring degradation of wastewater from nuclear power plant decontamination. The device for monitoring degradation of wastewater from nuclear power plant decontamination comprises a UV reactor connected to a first flow path and for UV-treating introduced wastewater; a wastewater degradation flow path for supplying the wastewater discharged from the UV reactor to the first flow path; a wastewater degradation detecting unit for analyzing components of the wastewater supplied from the wastewater degradation flow path and detecting whether a set condition is satisfied; and a purification flow path for purifying and supplying the wastewater supplied from the UV reactor to the first flow path when the set condition is satisfied.

Abstract: The present invention relates to a transport basket for defective spent nuclear fuel of a heavy water reactor and, more particularly, to a transport basket for defective spent nuclear fuel of a heavy water reactor that can reduce the burden of a personnel when handling spent nuclear fuel in a test facility by minimizing a storage space and maximizing a thickness such that only a predetermined amount of spent nuclear fuel for soundness evaluation in the test facility can be transported.

Abstract: A device for measuring large-area radioactive surface contamination can simultaneously obtain a plurality of detection values. The measurement device includes a frame body having a plurality of holes; a mover that is connected to, and moves, the frame body; and a plurality of radiation detectors that rest in the plurality of holes. The detectors detect one or more of: alpha rays, beta rays, or gamma rays. The location and level of radioactive contamination are accurately identified according to a comparison of the detection values of the plurality of radiation detectors.