Abstract: A mechanical decladder for a spent nuclear fuel rod-cut includes an opening and closing unit configured to open and close an outlet of a basket into which the nuclear fuel rod-cut is loaded, a supporter on which the nuclear fuel rod-cut discharged from the outlet of the basket is seated, a hydraulic cylinder module configured to move the nuclear fuel rod-cut seated on the supporter; and a cutting module for slitting the nuclear fuel rod-cut while the nuclear fuel rod-cut is being moved by the hydraulic cylinder module. The opening and closing unit opens and closes the outlet of the basket in conjunction with a movement of the hydraulic cylinder module.

Abstract: The present invention relates to a composition for removing a radionuclide, including: a first polymer including a hydroxy group; a second polymer into which a boronic acid group is introduced as a functional group; and an adsorbent for removing the radionuclide, and a method for removing a radionuclide using the same.

Abstract: An apparatus for detecting a leak sound in plant equipment using time-frequency transformation includes a first microphone measuring an acoustic signal generated in the plant equipment, a second microphone measuring an acoustic signal generated in the plant equipment, and a leak sound detection module detecting a leak sound in the plant equipment using time-frequency transformation of the acoustic signal measured by the first microphone and the acoustic signal measured by the second microphone, wherein a leak sound may be detected even when a transient dispersive noise signal, as well as a periodic noise signal, is large.

Abstract: The present invention relates to a magnetic cesium adsorbent, a preparation method therefor, and a cesium removal method using the same, the preparation method comprising the steps of: (a) preparing a metal hexacyanoferrate; and (b) hydrothermally reacting the metal hexacyanoferrate so as to prepare a metal hexacyanoferrate having a rhombohedral crystal structure.

Abstract: 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.

Abstract: An integrated monitoring system for radiological surveillance of groundwater and an operation method thereof are disclosed.

Abstract: The present invention relates to a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target.

Abstract: A radioactive cesium adsorbent includes photocatalyst particles and Prussian blue. The ferric ions of the Prussian blue are reduced to ferrous ions by activation of the photocatalyst particles. A method of removing radioactive cesium using the radioactive cesium adsorbent includes preparing a composition comprising photocatalyst particles and Prussian blue; preparing a precursor solution by mixing radioactive cesium and the composition prepared in the preparing of a composition; and reducing ferric ions of the Prussian blue to ferrous ions by activating the photocatalyst particles in the precursor solution prepared in the preparing of a precursor solution.

Abstract: Disclosed are a method of manufacturing a uranium target, the method including (a) a step of preparing a conjugate including a matrix and a uranium target green compact formed in the matrix; and (b) a step of performing thermo-mechanical treatment through additional heat treatment at 530° C. to 600° C. during a hot rolling pass in a process of hot-rolling the conjugate, and a method of extracting radioactive Mo-99 using the uranium target.

Abstract: An AhpF protein has thioredoxin reductase, peroxidase, and chaperone activities and is derived from Pseudomonas aeruginosa, and a use therefor. By using a novel activity of the AhpF of Pseudomonas aeruginosa according to the present invention, it is possible to produce a plant having strong resistance to various environmental stresses such as oxidative stress or heat stress, thereby making it possible to contribute to increasing crop productivity and mass production of useful constituents. In addition, it is possible to prevent desertification and environmental pollution through the development of transformed plants having resistance to high temperatures and drying.

Abstract: The present disclosure relates to an L-shaped header of a steam generator including a spiral heat transfer tube, and a coupling structure between the L-shaped header and the heat transfer tube, wherein an upper end and a lower end of a heat transfer tube assembly configured with a plurality of heat transfer tubes are vertically formed, and the upper and lower ends of the heat transfer tube assembly are vertically coupled to a bottom side or a top side of the header. Therefore, the heat transfer tubes constituting the same concentric circle may use the heat transfer tubes formed with the same shape, thereby improving the manufacturability of parts and reducing the manufacturing cost.

Abstract: A safety injection device includes a containment building, a reactor coolant system provided inside the containment building and accommodating a reactor coolant formed to carry heat energy generated according to fission of fuel, a cooling water storage section accommodating cooling water injected into the reactor coolant system, a power producing section producing power with steam discharged from the reactor coolant system in case of an accident, a steam supply pipe transmitting steam discharged from the reactor coolant system to the power producing section, a steam discharge pipe discharging steam drove the power producing section and a safety injection line supplying cooling water accommodated in the cooling water storage section to the inside of the reactor coolant system.

Abstract: The present invention relates to a plate heat exchanger and provides a heat exchanger and a nuclear power plant comprising same, the heat exchanger comprising: a plate unit having multiple plates overlapping one another; a flow path unit, which forms flow paths having fluids flowing therein by processing at least parts of the respective plates; and a detection flow path formed between the multiple plates so as to allow the fluids leaking from the flow paths to flow thereinto and formed so as to detect the leakage of the fluids from the flow paths.

Abstract: The present disclosure relates to a chromium-aluminum binary alloy with excellent corrosion resistance and a method of producing the same, and more particularly to a chromium-aluminum binary alloy with excellent corrosion resistance. The chromium-aluminum binary alloy may be easily produced and has ductility, thus being highly applicable as a coating material for a material requiring high-temperature corrosion resistance and wear resistance.

Abstract: The present invention provides a passive residual heat removal system and an atomic power plant comprising the same, the passive heat removal system comprising: a plate-type heat exchanger for causing heat exchange between a primary system fluid or a secondary system fluid which, in order to remove sensible heat from an atomic reactor cooling material system and residual heat from a reactor core, has received the sensible heat and the residual heat, and a cooling fluid which has been introduced from outside of a containment unit; and circulation piping for connecting the atomic reactor cooling material system to the plate-type heat exchanger, thereby forming a circulation channel of the primary system fluid, or connecting a steam generator, which is arranged at the boundary between the primary and secondary systems, to the plate-type heat exchanger, thereby forming a circulation channel of the secondary system fluid.

Abstract: A passive natural circulation cooling system according to the present invention can comprise: a passive condensation tank formed to accommodate cooling water; and a condensate water recirculation device provided at the inner part or upper part of the passive condensation tank, and condensing the cooling water such that the cooling water circulates inside the passive condensation tank. The condense water recirculation device can include: a duct extending upwards from the upper part of the passive condensation tank; and a plurality of partition plates provided inside the passive condensation tank or the duct.

Abstract: The application provides a self-diagnosis and accident-handling unmanned nuclear reactor, which: can passively cool down excessively generated heat without an operation of an operator when a malfunction of the nuclear reactor has occurred, wherein a cooling operation for safety measures can be carried out in a completely passive manner without a separate control command by a change in environmental conditions such as the structure and pressure of the nuclear reactor; and has a simpler structure compared to that of a conventional nuclear reactor safety system. It also provides a self-diagnosis and accident-handling unmanned nuclear reactor, which performs heat exchange by using a two-phase heat transfer mechanism, wherein heat exchange performance is maximized by introducing a spray-type heat exchanger having an optimized structure in which channels are three-dimensionally arranged, and can also easily and passively control heat exchange without a separate control means by using saturated steam pressure.

Abstract: The present disclosure provides a stopped cooling system including: a steam line connecting portion connected to a steam line so as to receive cooling water through the steam line connected to an outlet of a steam generator; a stopped cooling heat exchanger for receiving cooling water that enters the stopped cooling system through the steam line connecting portion, and discharging same through a passage of the heat exchanger; a stopped cooling pump activated to perform stopped cooling of the nuclear reactor upon normal stoppage of the nuclear reactor after primary cooling of the nuclear reactor cooling system or when an accident occurs, and for forming a circulating flow of cooling water that circulates between the steam generator and the stopped cooling heat exchanger; and a water supplying pipe connecting portion connected to the heat exchanger passage and a water supplying pipe, which is connected to the inlet of the steam generator, so as to supply the cooling water cooled in the stopped cooling heat exch

Abstract: A decontamination method that includes the steps of decontaminating an object containing radioactive contaminated metals or alloys with a chemical decontamination agent including sulfuric acid (H2SO4) and forming a Ba or Sr precipitate by adding a Ba or Sr cation and a hydroxylion or halogen anion salts to the decontamination waste water.

Abstract: The present disclosure relates to a radioactive material reduction facility, including a containment, a boundary section provided inside the compartment to partition an inner space of the containment into a first space for accommodating a reactor coolant system and a second space formed between the first space and the containment, and surround the reactor coolant system to prevent radioactive material discharged from the reactor coolant system or a line connected to the reactor coolant system inside the first space from being directly discharged into the second space during an accident, an in-containment refueling water storage tank (IRWST) installed between the first space and the second space and formed to accommodate refueling water, and a first discharge line formed to guide the flow of steam and radioactive material formed in the first space inside the boundary section into the in-containment refueling water storage tank.