The present invention relates to a method for identifying the unit causing a raw water leak in a condenser of a thermal power plant consisting of n units.

The present disclosure provides a sample holder assembly for a laser flash apparatus for measuring a thermal conductivity of a pebble-bed, the assembly comprising: a tubular sample container configured to be mounted on a sample carrier tube for the laser flash apparatus, wherein the sample container has open top and bottom; a bottom disc disposed in the sample container to block the open bottom of the sample container and configured for delivering a laser from a laser flash unit of the apparatus to a pebble-bed; the pebble-bed packed on the bottom disc to a predetermined thickness; and a top disc disposed on the pebble-bed and in the sample container to block the open top of the sample container and configured for receiving heat from the pebble-bed to transfer the heat upward.

Provided is a SiC semiconductor element equipped with a SiC integrated circuit having a stable characteristic, which operates normally even in a radiation environment. A radiation resistant circuit device includes: a SiC semiconductor element equipped with a SiC integrated circuit, a printed board on which the SiC semiconductor element is provided, a conductive wiring that is arranged inside the printed board and has a predetermined surface facing a bottom surface of a substrate electrode of the SiC integrated circuit, and an insulating material arranged between the bottom surface of the substrate electrode of the SiC integrated circuit and the predetermined surface of the conductive wiring.

Provided are a fuel placement confirmation method and a fuel placement confirmation apparatus that can increase an underwater imaging distance, collectively image a wide region, and reliably confirm an imprint number of a fuel assembly in consideration of a water fluctuation. A fuel placement confirmation apparatus 1 includes an imaging device 2 which images a fuel assembly number imprinted on a fuel assembly 27 loaded into a core 12; a movement device 5 which holds the imaging device 2 and performs scanning in a horizontal plane above the fuel assembly 27; and a fuel placement confirmation processing unit 3 which causes the movement device 5 to perform scanning, repeatedly executes imaging by the imaging device 2 on at least the fuel assembly 27 to be a placement confirmation target, selects image data not including image distortion from a plurality of acquired imaged images, combines the image data, generates entire image data 44 of at least the fuel assembly to be the placement confirmation target, and outputs the entire image data 44 to a display unit 8.

Provided are a fuel placement confirmation method and a fuel placement confirmation apparatus that can increase an underwater imaging distance, collectively image a wide region, and reliably confirm an imprint number of a fuel assembly in consideration of a water fluctuation. A fuel placement confirmation apparatus 1 includes an imaging device 2 which images a fuel assembly number imprinted on a fuel assembly 27 loaded into a core 12; a movement device 5 which holds the imaging device 2 and performs scanning in a horizontal plane above the fuel assembly 27; and a fuel placement confirmation processing unit 3 which causes the movement device 5 to perform scanning, repeatedly executes imaging by the imaging device 2 on at least the fuel assembly 27 to be a placement confirmation target, selects image data not including image distortion from a plurality of acquired imaged images, combines the image data, generates entire image data 44 of at least the fuel assembly to be the placement confirmation target, and outputs the entire image data 44 to a display unit 8.

A system for monitoring a reactor module housed in a reactor bay may include a mounting structure and one or more extendable attachment mechanisms connected to the mounting structure. Additionally, one or more monitoring devices may be operably coupled to the one or more extendable attachment mechanism, and the one or more extendable attachment mechanisms may be configured to selectively position the one or more monitoring devices at varying distances from a wall of the reactor bay to place the one or monitoring devices in proximity to the reactor module.

A system for monitoring a reactor module housed in a reactor bay may include a mounting structure and one or more extendable attachment mechanisms connected to the mounting structure. Additionally, one or more monitoring devices may be operably coupled to the one or more extendable attachment mechanism, and the one or more extendable attachment mechanisms may be configured to selectively position the one or more monitoring devices at varying distances from a wall of the reactor bay to place the one or monitoring devices in proximity to the reactor module.

The present invention discloses a nuclear reactor coolant pump that does not rely on an electric motor, but is operated by means of driving force generated inside a nuclear power plant, so a to be capable of maintaining the safety of the nuclear reactor when the nuclear reactor is operating normally and also in the event of an accident in the nuclear reactor. The nuclear reactor coolant pump comprises: a pump impeller rotatably installed in a first fluid passage of a nuclear reactor coolant system to circulate a first fluid inside the nuclear reactor coolant system; a drive unit receiving steam from a steam generator to generate driving force to rotate the pump impeller, and rotating about the same rotating shaft as the pump impeller to transfer the generated driving force to the pump impeller; and a steam supplying unit forming a passage between the steam generator and the drive unit to supply at least a portion of the steam released from the steam generator to the drive unit.

The present invention relates to a passive nitrogen injecting device for a nuclear reactor coolant pump, the device comprising: a nitrogen supply unit for supplying nitrogen; a pressure control valve for controlling the supply of nitrogen from the nitrogen supply unit according to pressure; an accumulator for filling the nitrogen supplied through the pressure control valve at a set pressure, and supplying the filled nitrogen in the event that an accident involving coolant loss occurs; and an isolation valve for controlling the supply of the nitrogen from the accumulator into a seal housing of a nuclear reactor coolant pump. The present invention uses an accumulator so as to be able to supply nitrogen by using the pressure in the accumulator without the supply of external power in the event of an accident involving coolant loss, and therefore has the effect of being able to improve safety.

The present invention relates to a passive nitrogen injecting device for a nuclear reactor coolant pump, the device comprising: a nitrogen supply unit for supplying nitrogen; a pressure control valve for controlling the supply of nitrogen from the nitrogen supply unit according to pressure; an accumulator for filling the nitrogen supplied through the pressure control valve at a set pressure, and supplying the filled nitrogen in the event that an accident involving coolant loss occurs; and an isolation valve for controlling the supply of the nitrogen from the accumulator into a seal housing of a nuclear reactor coolant pump. The present invention uses an accumulator so as to be able to supply nitrogen by using the pressure in the accumulator without the supply of external power in the event of an accident involving coolant loss, and therefore has the effect of being able to improve safety.