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 microgrid system includes a synchronous generator configured to convert mechanical power into electric power, an energy storage system configured to store and supply electric power, a controller configured to control operation of the energy storage system; and a point of common coupling bus connecting the synchronous generator and the battery energy storage system, wherein a controller parameter of the controller is determined based on a level of a disturbance using a trained artificial neural network in response to occurrence of the disturbance in the synchronous generator.

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: 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: A safety injection device includes a containment building, a reactor coolant system provided inside the containment building and accommodating a reactor coolant formed to carry heat energy generated according to fission of fuel, 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 drove 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.

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: 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: A reactor cooling and power generation system according to the present disclosure may include a reactor vessel, a heat exchange section formed to receive heat generated from a core inside the reactor vessel through a fluid, and an electric power production section including a Sterling engine formed to produce electric energy using the energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein 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, and operate even during a normal operation and during an accident of the nuclear power plant to produce electric power. Furthermore, the reactor cooling and power generation system according to the present disclosure may be continuously operated not only during a normal operation but also during an accident to perform reactor cooling, and produce emergency power, thereby improving the system reliability.

Abstract: A reactor cooling and power generation system according to the present invention includes a reactor vessel, a heat exchange section to receive heat generated from a core inside the reactor vessel through a fluid, and a power production section having a thermoelectric element configured to produce electric energy using energy of the fluid whose temperature has increased while receiving the heat of the reactor, wherein the system is configured to allow the fluid that has received the heat from the core to circulate through the power production section, and to operate even during an accident as well as during a normal operation of a nuclear power plant to produce electric power. Also, the reactor cooling and power generation system according to the present invention may continuously operate during an accident as well as a normal operation so as to cool the reactor and produce emergency power, thereby improving system reliability.

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.