Abstract: The present invention relates to a radionuclide adsorbent, which includes a hollow space (specifically, an area which is entirely empty or in which transition metal oxide particles are present); and a transition metal-ferrocyanide shell (specifically, a transition metal-ferrocyanide shell having a structure in which a plurality of two-dimensional nano flakes overlap or a transition metal-ferrocyanide shell having a structure in which a plurality of three-dimensional nano polyhedrons agglomerate) formed on the space surface, a preparation method thereof, and a method of removing a radionuclide using the same.

Abstract: Disclosed herein is a nuclear power plant main steam system that reduces the atmospheric discharge of radioactive materials generated in an accident. The system includes: a decontamination water tank containing decontamination water; and a connection pipe for connecting the decontamination water tank to a main steam pipe which connects a steam generator and a turbine. A main steam safety valve or a connection valve is provided as a three-way valve configured to discharge the generated steam to the atmosphere when an accident occurs within a design basis and to transfer the generated steam to the decontamination water tank when an accident involving damage to nuclear fuel occurs. The main steam system reduces discharge of radioactive materials to the atmosphere when a containment bypass accident (e.g., a steam generator tube rupture caused by high-temperature steam) occurs.

Abstract: The present invention relates to a prevention device for loss of coolant accident (LOCA) and a nuclear reactor having the same. The prevention device for LOCA includes a nozzle portion integrally formed in a reactor vessel and having a communication hole communicating with the inside of the reactor vessel, a nozzle finishing portion assembled to the nozzle portion and an injection line for injecting a fluid to the inside of the reactor vessel respectively on both sides thereof in a communicating manner, and a check valve mounting portion installed to be embedded inside the nozzle portion and having at least one check valve opened by flow such that the fluid is injected into the reactor vessel, wherein the check valve blocks outflow of a reactor coolant from the reactor vessel in case of failure of the injection line.

Abstract: The present disclosure describes a rotary pulsation generator having a simple structure capable of transferring fluid while implementing low noise and low vibration and having high flow of fluid and high pressure suction and discharge functions. According to the present disclosure, fluid is transferred by adjusting a width and interval of pulsation while reducing vibration caused by eccentric rotation of a rotor.

Abstract: The present invention relates to a method for simultaneous analysis of radiocarbon and tritium, the method including (i) mixing a radioactive waste sample containing a radiocarbon nuclide and tritiated water, and an oxidizing agent; (ii) oxidizing the radiocarbon nuclide in the radioactive waste sample to a gas containing an oxide of the radiocarbon nuclide by the oxidizing agent while suppressing volatilization of compounds containing gamma radionuclides other than the radiocarbon nuclide and tritium; (iii) discharging the gas containing an oxide of the radiocarbon nuclide by injecting an inert gas to the mixture; (iv) vaporizing and discharging the tritiated water in the mixture; and (v) analyzing radioactivity of radiocarbon and tritium from the discharged gas containing an oxide of the radiocarbon nuclide and tritiated water, and an apparatus for analysis of the same.

Abstract: The present disclosure relates to an apparatus for detecting nuclear reactor coolant leaks that is capable of maintaining radiation detection reliability and the integrity of a radiation detector from high-dose background radiation inside a nuclear reactor when a coolant leaks from the primary coolant system of the nuclear reactor. The apparatus of the present disclosure includes a shield having an internal space into which sample air containing a coolant leaking from a primary coolant system pipe of a nuclear reactor is introduced, and configured to close the exposed internal space or expand the internal space through detachable coupling; a first sensor disposed in the internal space to obtain a radiation measurement signal from the sample air; and a discriminator for determining whether a coolant is leaking based on the radiation measurement signal. This work was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (No.

Abstract: The present invention relates to a method for measuring radioactivity of radioactive waste, the method comprising an adsorption step (A) of selectively adsorbing a radioactive substance comprising at least one from among radioactive iodine and radioactive cesium from radioactive waste containing radioactive substances on an adsorption member for adsorbing a radioactive substance, and a measurement step (B) of measuring radioactivity of the radioactive substance.

Abstract: Provided are a composition for blocking radon and a method for preparing the same, and more particularly, to a composition for blocking radon including ethylene vinyl acetate (EVA); one or more polymer resins selected from the group consisting of polyurethane (PU) and silicone resin; and anionic surfactants, and a method for preparing a composition for blocking radon including irradiating radiation to the composition for blocking radon.

Abstract: The present disclosure provides a solidifying method of a radionuclide. The solidifying method of the radionuclide includes operations of: providing a low melting point glass including Bi2O3, B2O3, ZnO and SiO2; providing a glass mixture mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO4 and the low melting point glass; and heating the glass mixture.

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.

Abstract: The present invention relates to a method of preparing a live attenuated vaccine by irradiation and a live attenuated vaccine composition prepared by the same, and more particularly, a method of preparing a live attenuated vaccine by irradiation including irradiating a pathogenic microorganism with a dose of 0.5 to 2 kGy of radiation per single radiation six to fifteen times; and a live attenuated vaccine composition including a pathogenic microorganism attenuated to not be revertant to a wild type by generation of at least one mutation of nucleotide insertion and nucleotide deletion by irradiation.

Abstract: A heat exchanger includes a body having an inlet header through which a fluid is introduced, and an outlet header through which the fluid is discharged; and one or more plates accommodated in the body and provided with flow path modules providing flow paths for the fluid introduced through the inlet header to flow to the outlet header. The heat exchanger further includes at least one flow path adjuster each having at least a portion thereof accommodated in the body and being movable or rotatable to open or close a part or all of the flow paths or to change directions of the flow paths so that a flow of the fluid is adjusted.

Abstract: The present disclosure relates to a method for labeling a biomolecule, a fluorescent dye, or a nanoparticle compound with a radioisotope, comprising: (a) providing a cyclooctyne compound represented by the following formula (I) comprising the biomolecule, the fluorescent dye, or the nanoparticle compound which is bound to a cyclooctyne moiety of the cyclooctyne compound; and (b) reacting the cyclooctyne compound of formula (I) with a quinone compound represented by the following formula (II) to give a biomolecule, a fluorescent dye, or a nanoparticle compound labeled with the radioisotope: in formula (I), (Z is the biomolecule, the fluorescent dye, or the nanoparticle compound) in formula (II), (b is 0 or an integer from 1 to 10; L is CH2, —COO—, or —CONH—; M is the radioisotope).

Abstract: Disclosed are a nuclear fuel pellet having enhanced thermal conductivity and a method of manufacturing the same, the method including (a) a step of manufacturing a mixture including a nuclear fuel oxide powder and a thermally conductive plate-shaped metal powder; and (b) a step of molding and then heat-treating the thermally conductive plate-shaped metal powder to have an orientation in a horizontal direction in the mixture, thereby forming a pellet.

Abstract: Provided are an underwater radiation monitoring system and method. The monitoring system includes a plurality of sensors configured to measure a value of underwater radiation in a measurement area in which underwater radiation is to be measured, the plurality of sensors being installed in the measurement area by being arranged in a form which is set on the basis of information about the measurement area; and an electronic device configured to identify a value of underwater radiation in the measurement area on the basis of the values of underwater radiation measured by the plurality of sensors, wherein at least one first sensor among the plurality of sensors is connected to the electronic device to collect measured values obtained from the at least one first sensor and a plurality of second sensors excluding the at least one first sensor and to transmit the collected measured values to the electronic device.

Abstract: A method for training an apparatus for training a nuclide identification model is provided. In the method, nuclide data is classified into characteristics of energy spectrums for nuclides, training data is generated based on a number of data in each of the classified characteristics, and the nuclide identification model is trained by using the training data.

Abstract: The present invention provides a crucible for melting and casting a metal fuel, which includes a reaction preventing layer including: LaYO3; or ZrO2 containing a Y2O3 stabilizer at 5 to 10 wt %, and a method of melting and casting a metal fuel using the same.

Abstract: The present disclosure relates to a method for separating a carbon isotope and a method for concentrating a carbon isotope using the same, the method for separating a carbon isotope including: cooling a formaldehyde gas to a temperature of from 190K to 250K; and obtaining a mixed gas and residual formaldehyde by photodissociating the cooled formaldehyde gas, the mixed gas including carbon dioxide containing a carbon isotope and hydrogen.

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: The present invention relates to an anti-inflammatory composition and a composition for treatment of an inflammatory disease, both comprising a composite plant extract and, more particularly, to an anti-inflammatory composition comprising a composite plant extract including a Perilla frutescens extract and an Atractylodes macrocephala Koidzumi extract; a preparation method thereof; and a pharmaceutical composition comprising the composite extract for treatment of an inflammatory disease.