The present invention relates to a screen sharing system of a nuclear power plant main control room for improving operation safety of a power plant. According to an example of the present invention, a power plant control screen of each operator is shared in real-time among other operators by a simple manipulation such that operators can easily simultaneously check a power plant operation screen of other operators, whereby a mistake of another operator can be detected and manipulated in time, thus improving operation safety of a power plant.

The present invention relates to an abnormal driving state determination device using a neural network model, and the device can comprise: an abnormal driving state data generation unit for generating abnormal driving state data on the basis of information related to an abnormal driving state; an abnormal driving state learning unit which receives the abnormal driving state data so as to visualize the abnormal driving state data through a visualization algorithm, thereby allowing the abnormal driving state data to be learned by a neural network model; and an abnormal driving state determination unit including the neural network model for determining an abnormal state on the basis of the learned abnormal driving state data.

A transportable nuclear power generator assembly includes a first modular nuclear power generator unit and a second nuclear power generator unit. The first modular nuclear power generator unit includes a first transport container, a first nuclear power module positioned inside the first transport container, and a first supporting mechanism movably supports the first nuclear power module inside the first transport container. The second modular nuclear power generator unit includes a second transport container, a second nuclear power module positioned inside the second transport container, and a second supporting mechanism configured to support the second nuclear power module inside the second transport container. At least one of the first supporting mechanism and the second supporting mechanism is configured to move at least one of the first nuclear power module and the second nuclear power module relative to one another to result in an at least critical state or a subcritical state.

A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.

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.

A method for selecting components in a radiation tolerant electronic system, comprising, determining ionizing radiation responses of COTS devices under various radiation conditions, selecting a subset of the COTS devices whose radiation responses satisfy threshold radiation levels, applying mathematical models of the COTS devices for post-irradiation conditions to determine radiation responses to ionizing radiation; implementing a radiation-tolerant architecture using COTS devices from the selected subset, the implemented circuit may be tested for robustness to ionizing radiation effects without repeated destructive tests of the hardware circuit by using the mathematical models for simulating response to the ionizing radiation, and implementing a multi-layer shielding to protect the implemented circuit under various radiation conditions.

The present invention provides a method for early warning of an abnormality sign of a device, which includes device importance and warning validity determination, and a system therefor. The method for early warning of the abnormality sign of the device comprises: a first step of determining by an early warning processing apparatus whether a device monitoring signal value exceeds a normal operation range by using a weight value on the basis of monitoring-parameter-specific importance data which has been previously analyzed by an operator; a second step of generating a warning by the early warning processing apparatus when the device monitoring signal value exceeds the normal operation range; and a third step of determining by a warning determination apparatus whether the generated warning is a valid warning, which is subject to a warning analysis and to be traced.

A nuclear power plant having a protective superstructure including a first end region configured to cover a nuclear reactor in a containment structure, a second end region opposite the first end region and configured to cover a cooling water pump house, and a central region between the first and second end regions and configured to cover a turbine hall. The superstructure has an oval-shaped plan profile, the oval having a greater degree of curvature at the first end region than at the second end region.

A nuclear reactor is positioned on a barge which floats on the water of a water tank. The water tank includes a bottom wall, first and second end walls and first and second side walls. The bottom wall includes a lower layer of concrete, an intermediate layer of water impervious material positioned on the lower layer of concrete, and an upper layer of concrete positioned on the intermediate layer of water impervious material. Each of the first and second end walls and the first and second side walls includes an outer layer of concrete, an intermediate layer of water impervious material positioned at the inner side of the outer layer of concrete, and an inner layer of concrete material positioned at the inner side of the intermediate layer of water impervious material.

A nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.