Abstract: Provided is an apparatus for controlling a gain according to a water level change rate of a steam generator in nuclear power plants.

Abstract: A flexible display apparatus is provided. The flexible display apparatus includes: a display configured to display an object on a screen; an actuator configured to provide shape deformation to the display; and a controller configured to determine deformation information for reconfiguring and displaying the object, control the actuator to provide the shape deformation according to the determined deformation information, and control the display to reconfigure the displayed object and display the reconfigured object.

Abstract: A flexible display apparatus configured to sense deformation of the flexible display apparatus, control display of an object displayed on the flexible display apparatus based on the deformation, and execute operations based on the displayed object.

Abstract: Provided is a method of establishing, by a first display device, a communication link with a second display device, the method including operations of detecting a first bending motion occurring in the first display device; obtaining information about a second bending motion occurring in the second display device; and establishing a communication link for a data exchange with the second display device, based on a start time of the first bending motion and a start time of the second bending motion.

Abstract: A flexible display apparatus is provided. The flexible display apparatus includes a display configured to display content on a screen, a sensor configured to detect bending of the display from a first form to a second form, and a controller configured to reconstruct the content based on the bending and to display the reconstructed content in a first screen generated in one region of the display when it is determined that the display is restored to the first form.

Abstract: A flexible display apparatus includes a flexible display, a sensor which senses bending of the flexible display, and a controller which determines a screen activation region and a screen inactivation region from among a plurality of display regions of the flexible display based on the sensed bending, and displays a predetermined screen on the screen activation region.

Abstract: A method and apparatus are provided for releasing a locked state. A display unit displays a locked view including a plurality of affordance objects. When a user touches the display unit in a direction of the affordance objects in the locked view, a control unit controls the display unit to switch to an unlocked view while dispersing the affordance objects.

Abstract: Methods and apparatus are provided for releasing a locked state of a display apparatus. A display unit displays a locked view having an affordance object. When the affordance object is touched at a touch point, the control unit controls the display unit to switch to an unlocked view while tilting the affordance object in a direction corresponding to the touch point.

Abstract: A display apparatus including a display unit for displaying a lock view including an affordance object which represents a changeable natural phenomenon and a control unit for, when the affordance object is touched on the lock view, controlling the display unit to switch to an unlock view while changing the affordance object to display a change of the natural phenomenon in response to the touch.

Abstract: A method and apparatus are provided for releasing a locked state of a display apparatus. A display unit displays a locked view having a line and an affordance object connected to the line. When a user touches a point on the line in the locked view, a control unit controls the display unit to switch to an unlocked view while separating the affordance object by cutting the line at the point on the line.

Abstract: An apparatus for controlling an output of a pressure setting signal to automatically control a steam bypass control system includes a pressure setting signal output unit for outputting a pressure setting signal according to a cold leg temperature of a reactor coolant; a first logic value output unit for outputting a first logic value that is changed according to reactor power; a second logic value output unit for outputting a second logic value that is changed according to a temperature difference between an average temperature of the reactor coolant and a reference temperature; a NAND gate circuit unit for outputting an inverse logic value according to the first and second logic values; and a first output control unit for controlling whether to output the pressure setting signal according to the inverse logic value of the NAND gate circuit unit.

Abstract: A display device for enhancing user convenience includes a display unit which displays a screen divided into a plurality of areas displaying different types of objects thereon, and a control unit which changes sizes of the respective areas of the screen in relation to each other to avoid overlapping with each other, automatically reloads objects to be displayed on the changed areas from a source and reconstructs the screen, according to a user manipulation.

Abstract: A system and a method of transforming a gain and an integral time constant of a proportional-integral (PI) controller according to a timer lapse time to relieve an excessive phenomenon of a steam generator level caused by rapid changes in open degrees of a downcomer feed-water valve and an economizer feed-water valve when reactor power transfers between low and high power sections. Accordingly, an excessive phenomenon of a steam generator level is relieved at a transfer time when reactor power transfers between low and high power sections. Therefore, a possibility of a stop of a reactor caused by the excessive phenomenon of the steam generator level is reduced to relieve burden on an operator and improve an operation rate and economic feasibility of a nuclear power plant.

Abstract: Provided are a method and apparatus for validating dynamic performance of a control system of a nuclear power plant in operation, without performing a power ascension test. According to the present invention, when the performance of the control system requires to be validated in order to change a control logic or its setpoint of or to replace hardware of the control system, the dynamic performance of the control system may be validated without performing the power ascension test which can be performed only in a trial operation and requires large expenses. In the present invention, a design computer code capable of simulating a transient state of the nuclear power plant is connected to the hardware of the control system, and tests to be performed at the power ascension test or in the transient state of the nuclear power plant are simulated by directly using the hardware of the control system instead of a control system model of the design computer code, in an on-line state.

Abstract: Provided are a method and system for modeling a service using a Bayesian network and status information in a distributed environment. The method includes creating a scenario for modeling at least one service, categorizing the service into models according to properties based on the scenario, setting interrelationships including a chronological relationship, a hierarchical relationship, and correlation between the categorized models, and deriving information including a service goal and status information with respect to the models and completing service modeling. Accordingly, a service provider, which digitally provides various services in a ubiquitous environment, can efficiently and actively provide intelligent services. In addition, since a specific method of modeling a service based on probabilities is provided, an intelligent service is modeled efficiently and diversely.

Abstract: A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a flow error signal corresponding to a difference between a steam flow signal and a feedwater flow signal; and a water level correction error signal generator for generating a water level correction error signal corresponding to a sum of a water level measurement signal and the flow error signal.

Abstract: An ontology-based ad hoc service discovery system includes a local service cache, a cache manager, a service description unit, a query processor, a service semantic inference unit and a node daemon. The local service cache restores a service ontology by collecting class information of all services advertised on an ad hoc network and stores the service ontology. The cache manager manages the local service cache and performs various preset operations on the cache. The service description unit stores a description of a corresponding service for use in initializing the local service cache. The query processor starts performing a semantic based service query protocol by receiving a service query from a user or an application program. The service semantic inference unit inspects whether the service query transmitted from a client is coincident with the content of the service. The node daemon performs a service cache synchronization protocol with neighboring nodes.

Abstract: A feedwater control system considering a pressure drop of feedwater control valve in a nuclear power plant and a control method therefor are provided. In the feedwater control system, a first detection unit includes: a flow error signal generator for generating a flow error signal corresponding to a difference between a steam flow signal and a feedwater flow signal; and a water level correction error signal generator for generating a water level correction error signal corresponding to a sum of a water level measurement signal and the flow error signal.