Abstract: Provided is an apparatus for removing thermal stratification generated by turbulent penetration by using a rotation ring. The apparatus removes thermal stratification formed in a branch pipe branching from a main pipe through which a high-temperature fluid flows, the apparatus including: a hollow body portion coupled to the branch pipe; a plurality of first electromagnets provided to be spaced apart from each other in a circumferential direction of the body portion; a controller configured to sequentially change polarities of the plurality of first electromagnets; and a rotation ring including a plurality of second electromagnets having either an N polarity or an S polarity, the rotation ring being rotatably coupled to the body portion, wherein, when the polarities of the plurality of first electromagnets are sequentially changed, the rotation ring rotates according to a magnetic force of the plurality of first electromagnets and the plurality of second electromagnets.

Abstract: A cavitation reduction valve structure using a dispersion valve includes: a main valve including a front end portion to which a fluid is introduced, a rear end portion from which a fluid is discharged, and a body portion which is arranged between the front end portion and the rear end portion; a first actuator which is connected to the body portion and opens and closes the body portion and controls a flow rate passing through the body portion; a first dispersion pipe branching from the front end portion; a buffer portion which is connected to the first dispersion pipe; a second dispersion pipe connecting the buffer portion and the body portion to each other; a bypass pipe connecting the buffer portion and the rear end portion to each other; and a dispersion valve provided on the bypass pipe.

Abstract: A method of determining variable trip setpoints at the time of performing a safety analysis on a plant protection system includes: selecting a fixed analysis setpoint including a first analysis setpoint at which safety functions are initiated according to process variables of a power plant, and a first reaching time representing a time required to reach the first analysis setpoint; deriving a variable analysis setpoint satisfying conditions of the first fixed analysis setpoint; and determining a variable trip setpoint by reflecting uncertainty of an instrumentation and control system in relation to the variable analysis setpoint.

Abstract: An apparatus for generating electric power from the motion of a vehicle according to the disclosure includes: a magnetic fluid storage unit in which a magnetic fluid is stored and from which the magnetic fluid is discharged by a pressing force of the vehicle; a pipe unit through which the magnetic fluid discharged from the magnetic fluid storage unit moves; and an induction coil unit arranged to surround a circumference of the pipe unit so that an induced electromotive force is generated when the magnetic fluid moves.

Abstract: A power plant controlling method includes: receiving a beacon signal from a location beacon or a device information beacon, wherein the location beacon is mounted in a region of a power plant area requiring monitoring and controlling, the region including an employee circulation path, and the device information beacon is mounted at a device requiring identification; tracking a location of the beacon that transmitted the received beacon signal; and receiving information about devices within a radius set by a user based on the tracked location.

Abstract: The present disclosure relates to a transfer cask for transferring spent nuclear fuel. The transfer cask transfers a canister storing the spent nuclear fuel and includes a transfer container having a space for accommodating the canister; a neutron shielding body arranged on an outer periphery of the transfer container to shield neutrons; and an opening/closing portion that is coupled to a lower portion of the transfer container and opens and closes the lower portion of the transfer container, wherein the opening and closing portion, a support portion supporting the transfer container and having a first through hole in communication with the transfer container; a lid assembly having a first lid portion and a second lid portion that open and close the first through hole; and a base plate on which the support portion is seated and a second through hole through which the canister is drawn out is formed.

Abstract: The triple sealing device for an electronics housing of smart instrumentation includes: an electronic board; a first housing which has the electronic board disposed therein and includes a first inlet port to allow a cable to pass therethrough; a second housing which is provided above the first inlet port of the first housing and coupled to the first housing, and includes a second inlet port to allow a cable to pass therethrough; an elastic block provided on an inner circumferential surface of the second inlet port; and a cable which is connected to the electronic board and extends outward after passing through the first inlet port and the second inlet port.

Abstract: Provided is a secondary shutdown structure of a nuclear reactor, which uses sliding doors, and more particularly, to a secondary shutdown structure of a nuclear reactor, which uses sliding doors and is capable of shutting down a nuclear reactor reliably with a simple structure without using a boric acid solution.

Abstract: The present disclosure relates to a sliding type transfer cask for transferring spent nuclear fuel. The sliding type transfer cask includes a transfer container having a space for accommodating a canister; a neutron shielding body disposed around an outer circumference; and an opening/closing portion coupled to a lower portion of the transfer container. The opening/closing portion includes a support portion that has a first through-hole communicating with the transfer container and supports the transfer container; a base plate that is arranged below the support portion; and a lid assembly that includes a first lid portion and a second lid portion. The first lid portion includes a first lid and a first motor for sliding the first lid. The second lid portion includes a second lid and a second motor for sliding the second lid.

Abstract: Provided is an apparatus for evaluating a response time of a plant protection system. The apparatus includes: a classification module classifying a design process related to a response time requirement of each channel performing a safety function into four operations of a safety analysis operation, a system design operation, a response time analysis operation, and a response time test operation; and an integrated evaluation module determining whether a response time evaluation is proper based on a time t1 derived in the safety analysis operation, a time t2 derived in the system design operation, a time t3 derived in the response time analysis operation, and a time t4 derived in the response time test operation.

Abstract: Provided is a method of managing design bases applied to a nuclear power plant in an integrated manner by using a building information model so that design bases attributes are precisely provided to a subsequent design by using a design bases information layer to ensure consistency between design drawings.

Abstract: Provided is a power plant operation history device. The power plant operation history device includes: a communication unit configured to detect RFID of a wearable device and communicate with a signal conversion device; and a control unit configured to determine a power plant control authority of a user based on user identification information obtained through the communication unit, transmit an operation permission signal allowing operation of an input device of a power plant control facility control device to the signal conversion device when it is determined that the user's power plant control authority exists, and normally process a user input from the input device through the signal conversion device.

Abstract: A non-welded type branch piping reinforcement apparatus capable of preventing damage to a branch pipe system by increasing the strength of the branch pipe system by covering and protecting the branch pipe system connected to a header pipe, by a joint clamp, a connection pipe clamp, and a valve clamp includes: a joint clamp arranged to cover the branch pipe joint and the connection pipe and having an arc-shaped cross section; a connection pipe clamp arranged to cover the connection pipe and having an arc-shaped cross section; and a valve clamp arranged to cover the connection pipe and the valve and having an arc-shaped cross section, wherein one end of the connection pipe clamp is connected to the joint clamp and the other end of the connection pipe clamp is connected to the valve clamp.

Abstract: The modular lower moving system for nuclear fuel handling includes: a lower reactor vessel assembly including nuclear fuel loaded therein; a carrier having a space allowing the lower reactor vessel assembly to be accommodated therein; a rail extending from a reactor area to a fuel handling area; a transfer cart horizontally movable along the rail; a lifting device installed at the transfer cart, movable upward or downward with respect to the transfer cart; and a drive device configured to supply power to the transfer cart and the lifting device. The method of refueling nuclear fuel using the modular lower moving system includes a carrier lifting process, a lower reactor vessel assembly detachment process, a process of accommodating the lower reactor vessel assembly in the carrier, a carrier lowering process, a transfer cart movement process, a nuclear fuel offloading process, and a nuclear fuel loading process.

Abstract: Provided is a method of tracing a common cause failure in an integrated drawing. The method includes: synthesizing entities assigned attributes in at least one design drawing in units of a system where a common cause is to be traced; generating an integrated drawing with a hierarchical structure by horizontally or vertically interconnecting the entities assigned the same attribute in the at least one design drawing; and displaying a fault propagation path in the integrated drawing by using an internal tracer, wherein the displaying illustrates state information of the entities on the fault propagation path.

Abstract: Provided is an integrated drawing producing method for common cause tracing. The integrated drawing producing method includes: distinguishing shapes of entities in at least one design drawing and assigning an attribute to each of distinguished entities; synthesizing the entities assigned the attributes in the at least one design drawing in units of a system where a common cause is to be traced; and generating an integrated drawing with a hierarchical structure by horizontally or vertically interconnecting the entities assigned the same attribute in the at least one design drawing.

Abstract: According to an embodiment of the present disclosure, an apparatus of preventing a malfunction of a circuit breaker may include a circuit breaker and a variable resistor installed on a distributing board, the variable resistor being disposed outside the circuit breaker separately from the circuit breaker, wherein the variable resistor is connected in parallel to an anti-pumping auxiliary relay RW, and total resistance of the anti-pumping auxiliary relay RW and the variable resistor connected in parallel to each other is less than resistance of the anti-pumping auxiliary relay RW.

Abstract: A control valve pneumatic actuator using a transparent casing includes a casing having a cylindrical shape and made of a transparent material to enable an inside of the casing to be observed from outside, a driveshaft penetrating the inside of the casing, a diaphragm fixedly connected to the driveshaft inside the casing and vertically moving in the casing according to a movement of the driveshaft, a ring holder attached to an outer circumferential of the diaphragm and having a groove having a C-shape, a rubber ring inserted into the groove of the ring holder, a control valve connected to a lower portion of the drive shaft extending below the casing, and a yoke arranged below the casing and connecting the casing to the control valve.

Abstract: Provided is an installation structure for installing control rod drive mechanisms and cable sealing units in a nuclear reactor pressure vessel. The installation structure includes: a sealing flange having a ring shape and being hermetically coupled to an upper pressure vessel and a lower pressure vessel of the nuclear reactor pressure vessel; a cylindrical tube extending downward vertically from an internal edge of the sealing flange; and a support plate provided horizontally to block a lower end portion of the cylindrical tube. A plurality of mounting holes that penetrate through the sealing flange horizontally are arranged in the sealing flange with a predetermined interval therebetween along a circumferential direction, the cable sealing units are inserted and mounted in the plurality of mounting holes, and the control rod drive mechanisms are installed on the support plate to be supported.

Abstract: An apparatus for detecting a position of a control rod includes a control rod driving shaft having an outer circumferential surface on which position information is marked, a mirror configured to reflect the position information, and a detector configured to detect a position of the control rod driving shaft from the position information reflected from the mirror, when the control rod driving shaft moves vertically.