Abstract: A device for measuring a heat transfer rate according to the present invention includes: a first layer provided with a first material portion and a second material portion disposed in parallel in a surface direction of an object; a second layer provided with a third material portion disposed in parallel with the first material portion in a thickness direction of the first layer and having the same thermal conductivity as the second material portion, and a fourth material portion disposed in parallel with the second material portion in the thickness direction and having the same thermal conductivity as the first material portion; and a temperature measurement layer to measure a temperature difference in the surface direction between the first layer and the second layer, wherein the temperature measurement layer includes: a thermocouple portion provided with a first contact between the first material portion and the third material portion, and a second contact between the second material portion and the fourth

Abstract: The present invention relates to a composition for controlling plant diseases containing a limonene derivative as an active ingredient. In the present invention, the limonene derivatives have an effect of inhibiting the growth of Xanthomonas oryzae pv. Oryzae (Xoo), which is a pathogen mediating bacterial leaf blight, and Magnaporthe oryzae, which is a pathogen mediating rice blast, and it was confirmed in an experiment with respect to inhibition using volatility (i.e., in a state not being in direct contact with Xoo or M. oryzae) that the limonene derivatives have a growth inhibitory effect. Accordingly, the limonene derivatives have an inhibitory effect against the growth of Xoo and thus they can be effectively used as a composition for controlling plant diseases.

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: 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: A modulator includes: a high voltage transformer transforming a voltage supplied through a primary side and a secondary side to apply a current pulse to a driving device; a bipolar pulse generator applying a magnetizing pulse and a main pulse to a connection line connected to the primary side of the high voltage transformer; and a timing controller controlling a time difference of applying the magnetizing pulse and the main pulse, wherein the bipolar pulse generator includes a magnetizing pulse generation unit generating the magnetizing pulse by using positive power, and a main pulse generation unit generating a negative pulse by using negative power. Also, the modulator includes a pulse waveform controller in which a plurality of unit modules of the same structure is disposed in series through a small transformer on the secondary side of the high voltage transformer.

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 disclosure relates to a method of removing a nuclear power plant activation structure. Specifically, an embodiment of the present disclosure may provide a method of removing a nuclear power plant activation structure including flattening at least a portion of a wall surface of a peripheral portion of a wall of a nuclear reactor, the wall including a buried portion in which a nuclear power plant activation structure is buried and the peripheral portion circumferentially surrounding the buried portion; installing a drilling device in the flattened peripheral portion and performing a drilling operation; removing the nuclear power plant activation structure from the buried portion; and cutting the removed nuclear power plant activation structure and storing pieces of the cut nuclear power plant activation structure in a shielding container.

Abstract: The present invention relates to a zirconium alloy cladding with improved oxidation resistance at a high temperature and a method of manufacturing the same. More particularly, the zirconium alloy cladding includes a zirconium alloy cladding; and a Cr—Al thin film coated on the cladding, wherein the thin film is deposited through arc ion plating and the content of Al in the thin film is 5% by weight to 20% by weight.

Abstract: A heat transferring device includes a pumping structure, and more specifically, a heat transferring device having a pumping structure, in which a working fluid of a cooling part is movable in an upward direction without a separate power source, and capable of using gravity while recovering the working fluid, and applying various heat sources to a heating part. To this end, a heat transferring device includes a heating part configured to heat a liquid working fluid and change the liquid working fluid to a gas state, a cooling part configured to cool the gaseous working fluid supplied from the heating part and change the gaseous working fluid to a liquid state, a pressurizing part configured to allow the heating part and the cooling part to communicate with each other so that the gaseous working fluid pressurizes the liquid working fluid, and a recovery part configured to move the liquid working fluid supplied from the cooling part to the heating part.

Abstract: The present invention relates to a method for removing cesium in a clay mineral using hydrogen peroxide. According to the present invention, cesium in a clay mineral is removed using hydrogen peroxide, which serves to induce interlayer expansion of the clay mineral to allow a cation to easily enter an interlayer of the clay mineral, and thus cesium desorption efficiency can be further improved. Also, the method according to the present invention can be efficiently used to restore soil in residential areas widely contaminated with a radionuclide when a major accident such as Fukushima nuclear accident occurs as well as various sites of atomic energy facilities contaminated with a radionuclide. Also, since radiation-contaminated soil is treated with only hydrogen peroxide and cations, secondary environmental pollution caused by wastes can be significantly reduce and the waste disposing cost can also be saved.

Abstract: Provided are a method for treating sulfur hexafluoride and an apparatus for collecting and treating by-products. The method for treating sulfur hexafluoride, and the apparatus for collecting and treating by-products according to the present invention are a significantly effective method and apparatus capable of safely treating sulfur hexafluoride at low cost.

Abstract: A long-term cooling system in a nuclear power plant according to the present disclosure may include 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) disposed outside the boundary section and configured to store refueling water therein, an emergency cooling tank disposed outside the containment and provided with a condensation heat exchanger, a gas-liquid separator connected to the emergency cooling tank outside the containment, and a return line 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: Disclosed are a nuclear reactor long-term cooling system and a nuclear plant having the same. The nuclear reactor long-term cooling system, comprises: a lower containment area formed to enclose a reactor coolant system, and configured to prevent steam containing radioactive substances generated from the reactor coolant system from leaking to a path other than a discharge unit; an In-Containment Refueling Water Storage Tank (IRWST) disposed outside the lower containment area, and having refueling water stored therein; and a discharge pipe configured to connect the lower containment area to the IRWST, and to discharge steam of the lower containment area to the refueling water when an accident occurs. The nuclear plant may have an enhanced safety.

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. The connecting apparatus for a steam generator disposed between a steam generator and a flow mixing header and fastening the steam generator to the flow mixing header in a sealing manner includes: a baseplate mounted on the flow mixing header and 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 and allowing an outlet of the steam generator to be inserted and fastened thereto.

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: A method for detecting a radionuclide using energy spectrum data represented by a count depending on energy obtained from a radiation detector, including: calculating a count ratio for a particular energy value using a background energy spectrum data measured without a target object to detect the radionuclide and a target energy spectrum measured in the presence of the target object; and comparing a background count ratio and a target object count ratio, where the count ratio is a ratio of a low count sum of count values which is an energy value or less divided by a high count sum of the count values which is greater than the particular energy value, or a ratio of the low count sum of the count values which is smaller than the particular energy value divided by the high count sum of the count values which is the particular energy value or greater.

Abstract: The present invention relates to a passive infinite cooling system for a nuclear reactor and a method of operating the same. The system includes an energy release space in which a reactor vessel is accommodated, an energy absorbing space separated from the energy release space, an energy transfer space, which is provided above the energy absorbing space, absorbs and cools heat transferred from the reactor vessel, and discharges the absorbed heat to the outside through an outer wall thereof, a first cooling flow path through which the heat in the reactor vessel is transferred to the energy transfer space, a pressure balance pipe through which the pressure in the energy release space is transferred to the energy absorbing space, and a coolant spray pipe through which the cooling water in the energy absorbing space pressurized by the pressure balance pipe is transferred to the energy transfer space.

Abstract: A sensor tube according to the present disclosure includes a body including a body extension having opposite ends connected to measurement air connection pipes and an opening, the measurement air connecting pipes being connected to a humidity sensor to deliver moisture to the humidity sensor using measurement air or allow the measurement air released from the humidity sensor to flow therethrough, and the opening being formed in the body extension to cause an interior space of the body extension and the outside to be in communication with each other such that the moisture is introduced into the interior space of the body extension from the outside through the opening, and an opening/closing part that selectively opens or closes the opening by being operated by a difference in pressure between the interior space of the body extension and the outside.

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: There is provided a cooling apparatus for a molten core material, including: two or more cooling material containers disposed under a reactor vessel including a nuclear reactor core and including a cooling material therein; a first screen disposed under the two or more cooling material containers and including two or more first through-holes; and a second screen disposed under the first screen and including two or more second through-holes, wherein an average size of the two or more first through-holes is greater than an average size of the two or more second through-holes.