Abstract: An external reactor vessel cooling and electric power generation system according to the present invention includes an external reactor vessel cooling section formed to enclose at least part of a reactor vessel with small-scale facilities so as to cool heat discharged from the reactor vessel, a power production section including a small turbine and a small generator to generate electric energy using a fluid that receives heat from the external reactor vessel cooling section, a condensation heat exchange section 140 to perform a heat exchange of the fluid discharged after operating the small turbine, and condense the fluid to generate condensed water, and a condensed water storage section to collect therein the condensed water generated in the condensation heat exchange section, wherein the fluid is phase-changed into gas by the heat received from the reactor vessel.

Abstract: Provided are a system and method for reducing the atmospheric release of radioactive materials caused by a severe accident. The system includes a steam generator disposed in a containment building, configured to generate steam by using heat of a coolant heated in a nuclear reactor, and connected to a turbine through a main steam line, a decontamination tank connected to the main steam line through a connection line and containing decontamination water for decontaminating the steam delivered from the steam generator and reducing atmospheric release of radioactive materials when a severe accident occurs, and a depressurizing power generation unit disposed on the connection line and configured to generate emergency power while depressurizing the steam delivered from the steam generator toward the decontamination tank when the severe accident occurs.

Abstract: A safety injection device includes, 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 used to drive 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. In addition, cooling water accommodated in the cooling water storage section is supplied to the inside of the reactor coolant system, based on the power produced by the power producing section, through a cooling water inlet pipe connecting the cooling water storage section and the power producing section.

Abstract: The present invention relates to a nuclear fuel pellet laminate structure having enhanced thermal conductivity, including a nuclear fuel pellet; and a thermally conductive metal layer disposed above or below the nuclear fuel pellet, and a method for manufacturing the same.

Abstract: The present disclosure relates to a system and method for continuously supplying negative ions using multi-pulsed plasma sources. The system includes a plurality of plasma generators each to generate plasma by applying pulsed power to the electronegative gas from a gas source; a negative ion supply unit connected to the plasma generators to receive the plasmas transferred therefrom and to continuously supply ions; and a controller connected to the plurality of plasma generators and configured to control characteristics of the pulsed powers delivered to the respective plasma generators and to adjust phase shift associated with the pulsed power envelopes. By adjusting the phase shift, the controller enables a plasma in one of the plasma generators to be in an after-glow state when a plasma in another plasma generator is in an active-glow state.

Abstract: The present invention provides a fluid transfer apparatus comprising: a rotating shaft comprising a rotation unit extending along an axial direction and a first eccentric unit and a second eccentric unit disposed to be spaced apart from each other along the axial direction; a first rotor housing forming a first fluid compression space in the shape of an epitrochoid curved surface; a second rotor housing forming a second fluid compression space in the shape of an epitrochoid curved surface, and positioned to be spaced apart from the first rotor housing along the axial direction; a first rotor disposed in the first fluid compression space so as to delimit the first fluid compression space into multiple variable-displacement spaces, and coupled to the first eccentric unit while surrounding the first eccentric unit in the radial direction of the first eccentric unit; and a second rotor disposed in the second fluid compression space so as to delimit the second fluid compression space into multiple variable-displac

Abstract: Mineralogical method and apparatus for removal of cesium ion in aqueous solution are provided. In particular, a mineralogical method for removal of cesium ion in aqueous solution including controlling a temperature of radioactive wastewater containing cesium from 25 to 45° C., controlling an initial pH of the radioactive wastewater from 6.0 to 8.5, and adding iron(II) and sulfide(?II) containing sulfur in the ?2 oxidation state to the radioactive wastewater, to convert the cesium ion in aqueous solution into a cesium mineral, and a mineralogical apparatus for removal of cesium ion in aqueous solution, capable of being applied to such a method, are provided.

Abstract: The present disclosure relates to a method for labeling a radioisotope, a radiolabeling compound, a kit including the same, and a method for labeling a radioisotope, including: providing a diaminophenyl compound represented by Chemical Formula I below and including a biomolecule, a fluorescent dye or a nanoparticle compound bound thereto; and reacting the diaminophenyl compound and a radioisotope-labeled aldehyde compound represented by Chemical Formula II below at room temperature; and a related technology: in Chemical Formula I, A is CH2 or O; a is 0 or an integer of 1 to 10; X is CH2 or —CONH—; Y is CH2 or ?and Z is the biomolecule, the fluorescent dye or the nanoparticle compound, in Chemical Formula II, b is 0 or an integer of 1 to 10; and L is CH2 or —CONH—; and Q is M, M? and M? in Q are radioisotopes.

Abstract: A reactor cooling and power generation system according to the present disclosure includes a reactor vessel, a heat exchange section formed to receive heat generated from a core inside the reactor vessel, from a feedwater system through a fluid, and an electric power production section. A Stirling engine is provided to produce electric energy using the energy of the fluid whose temperature has increased while receiving the heat of the reactor. The system is formed to circulate the fluid that has received heat from the core in the heat exchange section through the electric power production section. The system operates even during a normal operation and during an accident of the nuclear power plant. The reactor cooling and power generation system accompanies a nuclear reactor vessel which includes a reactor coolant system, a feedwater system and a steam generator. A turbine produces electric power from the feed water system.

Abstract: A process for isolating 17O from water and a process for concentrating 17O by using the same are provided. The process for isolating 17O from water includes: mixing 17O-containing water with formaldehyde to prepare an aqueous formaldehyde solution; heating the aqueous formaldehyde solution to generate a vapor mixture containing water vapor and formaldehyde vapor; and obtaining 17O-depleted water, residual formaldehyde, and a gas mixture containing hydrogen and 17O-enriched carbon monoxide, through photodissociating the vapor mixture. An 17O-enriched water production process includes: an operation of adding hydrogen to the gas mixture to induce a catalytic methanation reaction to synthesize methane (CH4) and 17O-enriched water (H217O) through methanation, the operation being carried out following the process for isolating 17O from water.

Abstract: A chemical decontamination reagent containing a reducing agent, a reductive metal ion, and an inorganic acid is provided to remove a radioactive oxide layer on a metal surface. The reagent can dissolve the radioactive oxide layer on the metal surface effectively at a relatively low temperature and enables a simple process of contacting the reagent to the radioactive oxide, thus economically effective in terms of cost and time required for the process. Since the decontamination does not use a conventional organic chelating agent such as oxalic acid, but the reducing agent as a main substance, the residuals of the reducing agent remained after decontamination can be decomposed and removed with an oxidizing agent. Due to the easy decomposition with the chemical decontamination reagent, secondary wastes can be minimized and the radionuclides remained in the decontamination reagent solution can be removed effectively.

Abstract: A passive reactor cavity cooling system according to the present invention includes: a reactor cavity formed between a reactor vessel and a containment structure enclosing the reactor vessel; a first cooling system to control external air to sequentially pass through an air falling pipe and an air rising pipe provided in the reactor cavity, so that residual heat of a core transferred to the reactor cavity is discharged to the atmosphere; a second cooling system having a water cooling pipe disposed in an inner space of the containment structure or in a wall of the containment structure to discharge the residual heat of the core transferred to the reactor cavity to outside; and a functional conductor having an insulating property in a normal operation temperature range of the reactor and a heat transfer property in an accident occurrence temperature range of the reactor which is a higher temperature environment than the normal operation temperature range, wherein the air falling pipe and the water cooling pipe

Abstract: The present invention relates to a connecting apparatus for a steam generator disposed between a steam generator and a flow mixing header to fasten the steam generator to the flow mixing header in a sealed manner, and an integral reactor including the same. Fastening the steam generator to the flow mixing header in a sealing manner includes: a base plate mounted on the flow mixing header having a through hole formed at the center thereof; and a steam generator connecting portion protruding along the circumference of the through hole in the base plate allowing an outlet of the steam generator to be inserted and fastened thereto. Since the connection for the steam generator is tightly fastened to the flow mixing header, leakage of a coolant therebetween is prevented, and since the steam generator is horizontally disposed in the flow mixing header, structural stabilization may be achieved.

Abstract: The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.

Abstract: The present disclosure relates to a plasma generator having a matching apparatus for matching impedances, and an impedance matching method. The plasma generator includes an RF power supply unit, a load device part including a standard load having a predetermined impedance and an antenna-plasma device configured to generate plasma, and a matching unit configured to connect the RF power supply unit to any one of the antenna-plasma device or the standard load, and match impedances of the RF power supply unit and the antenna-plasma device when the RF power supply unit is connected to the antenna-plasma device, wherein the matching unit is configured to detect a parasitic impedance according to parasitic components inside a circuit by connecting the standard load and the RF power supply unit, connect the antenna-plasma device, when the parasitic impedances are detected, calculate reactance required for the impedance matching, and change capacitance.

Abstract: The present invention relates to an apparatus for determining the location of a radiation source. The apparatus for determining the location of a radiation source according to the present invention comprises: a collimator part for selectively passing radiation therethrough according to the direction in which the radiation is incident; a scintillator part for converting the radiation incident from the collimator part into a light ray; a first optical sensor for converting the light ray incident from one end of the scintillator part into a first optical signal; a second optical sensor for converting the light ray incident from the other end of the scintillator part into a second optical signal; and a location information acquisition part for acquiring information on the location where the light ray is generated in the scintillator part, by using the second optical signal and the second optical signal.

Abstract: An in-vessel cooling and power generation system according to the present disclosure may include a small scale reactor vessel, a heat exchange section provided inside the reactor vessel, and formed to supply supercritical fluid to receive heat from a reactor coolant system in the reactor vessel, an electric power production section comprising a supercritical turbine formed to produce electric energy using the energy of the supercritical fluid whose temperature has increased while receiving heat from the reactor coolant system, a cooling section configured to exchange heat with the supercritical fluid discharged after driving the supercritical turbine to shrink a volume of the supercritical fluid, wherein the supercritical fluid that has received heat from the reactor coolant system in the heat exchange section is formed to circulate through the electric power production section, and the cooling section.

Abstract: In an apparatus for evaluating reliability of a nuclear power plant operator, an expected task finishing time for each task of the operator is calculated based on input data for reliability evaluation of the operator to determine a task completion time for each task of the operator based on the calculated expected task finishing time and the input data. An initial time for the tasks is determined based on the input data and the task completion time for a current task. A total execution time of the operator is calculated based on the determined task completion time and initial time. An available time allowed for the operator to complete the tasks is calculated based on a predetermined allowed time and the determined initial time. A task failure probability is obtained from the difference between the calculated total execution time and the calculated available time based on probability distribution information.

Abstract: The present invention relates to an apparatus for determining the location of a radiation source. The apparatus for determining the location of a radiation source according to the present invention comprises: a collimator part for selectively passing radiation therethrough according to the direction in which the radiation is incident; a scintillator part for converting the radiation incident from the collimator part into a light ray; a first optical sensor for converting the light ray incident from one end of the scintillator part into a first optical signal; a second optical sensor for converting the light ray incident from the other end of the scintillator part into a second optical signal; and a location information acquisition part for acquiring information on the location where the light ray is generated in the scintillator part, by using the second optical signal and the second optical signal.

Abstract: A sensor tube according to the present invention comprises: a tubular body for connecting two connection pipes to each other, wherein the two connection pipes are connected to a humidity sensor, so that the connection pipes transfer steam to the humidity sensor by using circulating air or air discharged from the humidity sensor flow in the connection pipes; and a cover surrounding at least a part of the outer surface of the body to prevent foreign substances having a predetermined size or larger from passing, wherein the body is formed as a porous sintered body which allows stream to be introduced from the outside of the body into the body and be transferred by the circulating air.