Abstract: The present invention relates to a passive heat removal system which circulates cooling fluid to a steam generator via a main water supply line connected to the lower inlet of the steam generator, and a main steam pipe connected to the top outlet of the steam generator, to remove sensible heat of a nuclear reactor coolant system and residual heat of a core. The heat removal system comprises supplementary equipment for receiving surplus cooling fluid or for supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range. The supplementary equipment comprises: a supplementary tank, installed at a height between the lower inlet and the top outlet of the steam generator; a first connection pipe, connected to the main steam pipe and the supplementary tank; and a second connection pipe, connected to the supplementary tank and the main water supply pipe.

Abstract: The present invention relates to a three-dimensional surface image generating method and system using a multi-energy X-ray image and an optical image, and more particularly, to a three-dimensional surface image generating method and system using a multi-energy X-ray image and an optical image which reconstruct an X-ray tomographic image with an improved contrast of soft tissue including skin of an object using two or more multi-energy X-ray transmission data, calculate a three-dimensional surface model for the object, and combine optical image information including color information of the object to generate a three-dimensional surface image for the object.

Abstract: The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same. The emergency cooling tank cooling system includes an emergency cooling tank, a heat exchanging device installed to be exposed to an outside of the emergency cooling tank to operate in air, and configured to externally emit such that the operation of the emergency cooling tank is continued even without refilling the cooling water, and an opening and closing unit installed at an upper portion of the emergency cooling tank to be located higher than a water level of the cooling water.

Abstract: The present invention relates to a three-dimensional surface image generating method and system using a multi-energy X-ray image and an optical image, and more particularly, to a three-dimensional surface image generating method and system using a multi-energy X-ray image and an optical image which reconstruct an X-ray tomographic image with an improved contrast of soft tissue including skin of an object using two or more multi-energy X-ray transmission data, calculate a three-dimensional surface model for the object, and combine optical image information including color information of the object to generate a three-dimensional surface image for the object.

Abstract: Disclosed is a nuclear power plant which drives a Stirling engine by means of heat generated in nuclear power plant safety systems during an accident, uses the resulting power directly or generates electric power so as to supply the power to the safety systems, and thus can improve economic efficiency as well as the reliability of safety systems, such as a passive safety system, by operating the safety systems without an emergency diesel generator or external electric power.

Abstract: The present invention relates to a breast cancer diagnosis device. More particularly, the present invention relates to a breast cancer diagnosis device for early detection of the presence or absence of breast cancer lesions inside the breast of a diagnosis subject. The breast cancer diagnosis device includes: an X-ray diagnosis unit generating an X-ray image of a diagnosis subject; an optical diagnosis unit generating an optical transmission image of the diagnosis subject; and a transfer unit which is coupled to the X-ray diagnosis unit and the optical diagnosis unit to transfer all or part of the X-ray diagnosis unit and the optical diagnosis unit, and sequentially transfer all or part of the X-ray diagnosis unit or the optical diagnosis unit toward the diagnosis subject.

Abstract: A separate type safety injection tank comprises: a coolant injection unit connected to a reactor coolant system by a safety injection pipe such that coolant stored therein is injected into the reactor coolant system by a pressure difference from the reactor coolant system when a loss-of-coolant-accident (LOCA) occurs; a gas injection unit connected to the coolant injection unit, and configured to pressurize the coolant injected into the reactor coolant system, by introducing gas stored therein to an upper part of the coolant injection unit in the loss-of-coolant-accident; and a choking device disposed between the coolant injection unit and the gas injection unit, and configured to contract a flow cross-sectional area of the gas introduced to the coolant injection unit, and configured to maintain a flow velocity and a flow rate of the gas introduced to the coolant injection unit as a critical flow velocity and a critical flow rate when a pressure difference between the coolant injection unit and the gas inject

Abstract: The present disclosure may disclose a multi stage safety injection device, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance between the reactor vessel and the safety injection tank, and a set of safety injection lines connected to the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and connected to the safety injection tank with different heights to reduce a flow rate of coolant injected into the reactor vessel step by step according to the water level reduction of the safety injection tank in order to inject coolant to the reactor vessel at multi stages.

Abstract: The present disclosure relates to a passive safety system which uses a heat exchanger together with a thermoelectric element, and a nuclear power plant comprising the same. Disclosed are a passive safety system and a nuclear power plant comprising the same, the passive safety system comprising: a heat exchanger; a thermoelectric element; and a fan unit. The heat exchanger is formed at a space inside or outside a sealed housing, and in the heat exchanger, atmosphere is introduced and heat exchange is carried out in order to lower the pressure or temperature of the atmosphere inside the housing if an accident occurs in a reactor coolant system or a secondary system disposed inside the housing.

Abstract: The present disclosure may disclose a multi stage safety injection device and a passive safety injection system having the same, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance state between the reactor vessel and the safety injection tank, a safety injection line connected to a lower end portion of the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and a flow control line extended from the safety injection line to an inner portion of the safety injection tank, and provided with safety injection ports into which coolant is injected at predetermined heights, respectively, to reduce the flow rate of coolant

Abstract: The present invention relates to a passive heat removal system which circulates cooling fluid via a main water supply line, connected to the lower inlet of a steam generator, and a main steam pipe, connected to the top outlet of the steam generator, to the steam generator, in order to remove sensible heat of a reactor coolant system and residual heat of a core, the passive heat removal system comprising: supplementary equipment for receiving surplus cooling fluid or supplying supplementary cooling fluid in order to maintain the flow rate of the cooling fluid within a predetermined range, wherein the supplementary equipment comprises: a supplementary tank, installed at a predetermined height between the lower inlet and the top outlet of the steam generator, for receiving the surplus cooling fluid or supplying the supplementary cooling fluid, passively, depending on the flow rate of the cooling fluid; a first connection pipe, connected to the main steam pipe and the supplementary tank, for forming a flow path t

Abstract: The present invention discloses a passive cooling system of a containment building, to which a plate-type heat exchanger is applied. A passive cooling system of a containment building comprises: a containment building; a plate-type heat exchanger provided to at least one of the inside and the outside of the containment building and comprising channels respectively provided to the both sides of a plate so as to be arranged dividedly from each other such that the plate-type heat exchanger carries out mutual heat exchange between the internal atmosphere of the containment building and a heat exchange fluid while maintaining a pressure boundary; and a pipe connected to the plate-type heat exchanger by penetrating the containment building so as to form the path of the internal atmosphere of the containment building or the heat exchange fluid.

Abstract: A display device includes pixel circuits with light emitting devices coupled to a first voltage and a second voltage; a signal controller configured to: generate output image data by gamma converting and by decreasing input image data of a frame according to a gamma curve; and generate a control signal to display an image on the panel according to the generated output image data; a voltage difference setting unit configured to detect a maximum value in the output image data, and configured to calculate a difference value between the first voltage and the second voltage so that a driving current corresponding to the maximum value is generated; and a power supply unit configured to generate and apply the first and second voltages to the panel, the generated first and second voltages corresponding to the calculated difference value, wherein the gamma curve comprises one or more inflection points.

Abstract: A safety driving system of a display device includes a display panel including at least one conductive detection line, the conductive detection line extending in a predetermined area of the display panel and being configured to detect voltage variation according to damage in the predetermined area, a panel detector configured to apply a reference voltage to one end of the detection line, to receive an output voltage corresponding to the reference voltage through the detection line from another end of the detection line, to compare the received output voltage with a predetermined normal voltage range, and to generate and output a detection result signal, and a controller configured to provide a detection set value for driving the panel detector and to interrupt the driving of the display panel when the output detection result signal indicates that the display panel is damaged.

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 power supply device includes a first power generator, a second power generator, and a power selector. The first power generator generates a first power voltage of a first voltage level in a first display mode and a second voltage level in a transition period between the first display mode and a second display mode. The second power generator generates a second voltage. The power selector selects a driving power to provide the first power voltage to a power supply line in the first display mode, the second power voltage to the power supply line in the second display mode, and the first power voltage and the second power voltage to the power supply line in the transition period.

Abstract: Disclosed is a heat exchanger for a passive residual heat removal system, which improves heat transfer efficiency by expanding a heat transfer area. A heat exchange tube includes a first member connected to a steam pipe through which steam generated from a steam generator of a nuclear reactor circulates, and a second member connected to both of the first member and a feed water pipe used to supply water to the steam generator provided in the nuclear reactor, and the first member has the shape different from that of the second member, thereby expanding the heat transfer area so that the heat transfer efficiency is improved.

Abstract: A display device includes pixel circuits with light emitting devices coupled to a first voltage and a second voltage; a signal controller configured to: generate output image data by gamma converting and by decreasing input image data of a frame according to a gamma curve; and generate a control signal to display an image on the panel according to the generated output image data; a voltage difference setting unit configured to detect a maximum value in the output image data, and configured to calculate a difference value between the first voltage and the second voltage so that a driving current corresponding to the maximum value is generated; and a power supply unit configured to generate and apply the first and second voltages to the panel, the generated first and second voltages corresponding to the calculated difference value, wherein the gamma curve comprises one or more inflection points.

Abstract: The present disclosure provides a cooling system of an emergency cooling tank, which enables long-term cooling without refilling cooling water, in case of the change in a quantity of heat transferred to the emergency cooling tank according to a lapse of time upon an occurrence of an accident of a nuclear reactor, and a nuclear power plant having the same.

Abstract: The present disclosure may disclose a multi stage safety injection device and a passive safety injection system having the same, including a safety injection tank formed to contain coolant to be injected into a reactor vessel by a gravitational head of water when an accident occurs in which the pressure or water level of the reactor vessel is decreased, a pressure balance line connected to the reactor vessel and safety injection tank to form a pressure balance state between the reactor vessel and the safety injection tank, a safety injection line connected to a lower end portion of the safety injection tank and the reactor vessel to inject coolant to the reactor vessel in a pressure balance state between the reactor vessel and the safety injection tank, and a flow control line extended from the safety injection line to an inner portion of the safety injection tank, and provided with safety injection ports into which coolant is injected at predetermined heights, respectively, to reduce the flow rate of coolant