Abstract: An apparatus for eliminating residual heat of a nuclear reactor for vehicle mounting include: a reactor vessel in which molten salt flows; and a reactor cooler for cooling the reactor vessel. The reactor cooler includes: a first cooling unit including a heat medium that exchanges heat with the reactor vessel, and one or more heat dissipation pipes providing passages through which water coolant flows; and a second cooling unit configured to receive the water coolant discharged from the first cooling unit and cool the water coolant through an external fluid. The second cooling unit is configured such that the cooled water coolant flows into the first cooling unit in a normal position and in an abnormal position inclined to be perpendicular to the normal position.

Abstract: A multi-stage float sorting device includes a first flotator float-sorting ores mixed with water based on a difference in density, and a second flotator provided with a column extending in a top-down direction, one side of which communicates with the first flotator to receive primary concentrates, and float-sorts the primary concentrates based on a difference in density to obtain secondary concentrates. The second flotator includes a washing water jetting section provided at a top of the column to jet washing water, a gas sparger provided at a bottom of the column to jet an inert gas, and an opening and closing section located between the washing water jetting section and the gas sparger to partition an inside of the column into upper and lower regions, and form an opening for rising secondary concentrates in the column according to a pressure state of the lower region.

Abstract: A passive cooling system for a nuclear reactor includes an energy release space in which a reactor vessel is accommodated, an energy absorbing space separated from the energy release space, and an energy transfer space above the energy absorbing space and configured to absorb and cool heat transferred from the reactor vessel and discharge the absorbed heat to an outside of the system through an outer wall thereof. The passive cooling system further includes a first cooling flow path configured to transfer the heat in the reactor vessel to the energy transfer space, a pressure balance pipe configured to transfer the pressure in the energy release space to the energy absorbing space therethrough, and a coolant spray pipe configured to transfer the cooling water in the energy absorbing space pressurized by the pressure balance pipe to the energy transfer space may be provided.

Abstract: According to an embodiment, a wick structure of a heat pipe that is capable of bending while increasing a heat transferring operation limit value is provided by improving the wick structure provided inside the heat pipe.

Abstract: The present invention relates a security screening device, comprising: a radiation generator for respectively generating X-rays and neutron beams and irradiating same toward an inspection object; an inspection object transfer unit for changing the position of the inspection object; a radiation detector configured to respectively detect X-rays and neutron beams transmitted through the inspection object; and a gamma ray detector installed adjacent to the inspection object and configured to detect a gamma signal generated from the inspection object, wherein the radiation detector acquires image information of the inspection object by using radiation information detected from the X-rays and neutron beams that have passed through the inspection object, and the gamma ray detector analyzes the detected gamma ray to detect the location of the inspection object from the analysis of the inspection object and the image information.

Abstract: A cooling system in a nuclear power plant is disclosed, including a boundary section disposed inside a containment to enclose a reactor coolant system, and configured to restrict steam containing radioactive materials generated in the reactor coolant system from leaking into paths other than a discharge part. An In-Containment Water Storage Tank (IRWST) is disposed outside the boundary section and is configured to store refueling water therein. An emergency cooling tank is disposed outside the containment and is provided with a condensation heat exchanger. A gas-liquid separator is connected to the emergency cooling tank outside the containment. A return line is configured to connect the gas-liquid separator and the boundary section such that condensate generated by condensing the steam within the boundary section, through the emergency cooling tank and the gas-liquid separator, is discharged toward the boundary section upon an occurrence of a nuclear power plant accident.

Abstract: An image processing method includes: calculating a rotation matrix to eliminate vertical parallax by converting stereo image captured by stereo camera as if it is image captured by camera rotated about an origin of camera coordinate system, wherein the stereo image includes left image obtained by left camera and right image obtained by right camera; calculating a rotation matrix to adjust the horizontal parallax of the left image and a rotation matrix to adjust the horizontal parallax of the right image; calculating a geometric transformation matrix for the stereo image based on each camera characteristic matrix representing lens characteristics, the rotation matrix for eliminating vertical parallax, and the rotation matrices for adjusting horizontal parallax; and generating new stereo image in which vertical parallax is eliminated and horizontal parallax is adjusted by performing image warping for the stereo image captured by the stereo camera based on the calculated geometric transformation matrix.

Abstract: Air purification apparatuses and methods are provided. An air purification apparatus includes an air purification chamber and a supply chamber coupled to the air purification chamber. The air purification chamber includes a purification reactor, a first electron accelerator that irradiates a first electron beam to the purification reactor, and a second electron accelerator that irradiates a second electron beam to the purification reactor. The supply chamber includes a power supply that supplies power to each of the first electron accelerator and the second electron accelerator. The second electron accelerator is opposite to the first electron accelerator across the purification reactor.

Abstract: The fluid transfer apparatus includes a rotor housing for forming a fluid compression space having the shape of an epitrochoid surface; a rotor eccentrically rotates inside the fluid compression space by being eccentrically coupled to a rotation shaft; and a rotor housing cover covering the fluid compression space of the rotor housing and including a rotation shaft penetration hole formed at the center of the cover, and a first cover fluid channel and second cover fluid channel are symmetrically formed on the opposite sides of each other with the rotation shaft penetration hole in the middle, wherein a plurality of rotor housing covers are arranged to be spaced apart from each other, one rotor housing is arranged between every two rotor housing covers, one rotor is arranged in the fluid compression space of each rotor housing, and each rotor is arranged to face a different direction from a neighboring rotor.

Abstract: The present disclosure relates to a method of removing a radioactive structure from a nuclear power plant. The method includes flattening at least a portion of an outer surface of a drilling portion of a wall of a nuclear reactor vessel when the portion of the outer surface is uneven, wherein the radioactive structure is buried in the wall and the drilling portion is adjacent to the radioactive structure, installing a drilling device in the flattened drilling portion and performing a drilling operation, extracting the radioactive structure from the wall, and cutting the extracted radioactive structure and storing pieces of the cut radioactive structure in a shielding container.

Abstract: A nuclear reactor cooling system comprises a containment area, an In-Containment Refueling Water Storage Tank (IRWST), and a discharge pipe. The containment area is formed to enclose a reactor coolant system. The IRWST is disposed outside the containment area. The discharge pipe discharges steam from the containment area to refueling water in the IRWST when an accident occurs. A steam intake pipe has one end in fluid connection with an upper space of the IRWST, and another end in fluid connection with a radioactive substance reduction tank which stores cooling water. The steam intake pipe allows steam to flow from the upper space of the IRWST into the cooling water in the reduction tank.

Abstract: A steam generator accident mitigation system is disclosed. A steam generator accident mitigation system to mitigate an accident if the accident occurs in a steam generator installed inside a containment building of a nuclear power plant according to an exemplary embodiment of the present system, the system including: a pressurizing tank which is installed inside the containment building and includes a first cooling water and a non-condensable gas for pressurizing the first cooling water therein; at least one connecting pipe connecting the steam generator and the pressurizing tank; and at least one connecting pipe valve which is installed in the at least one connecting pipe, respectively, and is able to control the amount of opening of the connecting pipe; wherein opening of the at least one connecting pipe valve permits fluid communication between the steam generator and the pressurizing tank.

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: An electric gripping device is provided. The electric gripping device improves a coupling relationship between a two-fingered clamper module using a four-joint link and the actuator module to facilitate assembling and disassembling of the actuator module and the clamper module and minimizes a length of the electric gripper to easily secure a robot's work space or work direction when being connected to the robot.

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: The present invention relates to a radioactive chemical waste treatment apparatus including an adsorption unit including an radioactive chemical waste adsorption member for adsorbing and separating radioactive chemical wastes from radioactive chemical waste-containing fluid, and a regeneration unit which is in fluidic communication with the adsorption unit and is for regenerating the radioactive chemical waste adsorption member by desorbing the radioactive chemical wastes from the adsorption member with the radioactive chemical wastes adsorbed thereonto, and to a radioactive chemical waste treatment method including (A) adsorbing radioactive chemical wastes onto a radioactive chemical waste adsorption member and separating the radioactive chemical wastes from a radioactive chemical waste-containing fluid, and (B) desorbing the radioactive chemical wastes from the radioactive chemical waste adsorption member with the radioactive chemical wastes adsorbed thereonto, and regenerating the radioactive chemical wast

Abstract: There is provided an ultrafast electron diffraction apparatus including: a photoelectron gun configured to emit an electron beam; a bending portion for emitting the electron beam emitted from the photoelectron gun by changing a travel direction of the electron beam by a predetermined angle; and a sample portion including a sample to be analyzed by the electron beam emitted from the bending portion. The electron beam reaches the sample portion in a state that a pulse of the electron beam is compressed and the timing jitter between the pumping light and probe electron pulse is completely reduced as the travel direction of the electron beam is changed by the predetermined angle through the bending portion.

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: 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: 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.