4 results about "Nuclear power reactor" patented technology

This invention discloses a calibration device for a reactor pressure vessel inspection robot, comprising a nozzle area calibration component and a cylinder area calibration component that work together to perform remote ultrasonic calibration. This reactor pressure vessel inspection robot calibration device enables remote in-situ ultrasonic calibration, replacing the traditional equipment effluent calibration mode. It avoids the cumbersome process of equipment effluent, calibration, and re-entry, significantly shortening the critical path duration of nuclear power reactor pressure vessel overhauls and improving overall overhaul efficiency. The nozzle area calibration component is fixed to the inspection robot's support legs via a connecting backplate and can be hoisted into and out of the water along with the robot. This eliminates the need for separate scheduling of hoisting resources for the nozzle area test block and eliminates the need for personnel to perform long-pole remote operations on the reactor pool bridge platform, significantly reducing the time spent on hoisting and re-entry of hoisting and bridge resources. The auxiliary installation components of the cylinder area calibration component can adapt to multiple operating conditions, expanding the device's applicability.

This invention discloses a refueling system and method for a small nuclear power reactor. The system, located within the reactor building, includes a reactor pool, a spent fuel pool, and a fuel transfer channel. The spent fuel pool comprises a spent fuel storage area and other storage areas separated by walls lower than the spent fuel pool itself. The fuel transfer channel is a passage enclosed by walls and extends from the bottom of the spent fuel pool to the reactor pool. During refueling, the water in the reactor pool and spent fuel pool is at the refueling level, which is higher than the walls. The reactor pool is connected to the spent fuel pool via the fuel transfer channel, and the spent fuel storage area is connected to the other storage areas. After refueling, the water in the reactor pool and fuel transfer channel is drained, and the spent fuel pool is drained to the storage level, which is lower than the walls. The reactor pool and spent fuel pool, as well as the spent fuel storage area and other storage areas, are now isolated. This invention improves the reliability of the refueling system.

The application discloses a zirconium alloy cladding for nuclear power reaction accident fault-tolerant fuel and a preparation method thereof. The zirconium alloy cladding for nuclear power reaction accident fault-tolerant fuel comprises a zirconium alloy base material, and a zirconium oxide bottom film layer and an aluminum-zirconium mixed film layer are sequentially arranged on the surface of the zirconium alloy base material. The zirconium alloy cladding for nuclear power reaction accident fault-tolerant fuel has excellent interface bonding between layers, uniform thickness of each layer, compact structure, and finally has good corrosion resistance, wear resistance and high-temperature water vapor corrosion resistance.

The application relates to a supporting system for a half-pool type loop nuclear power reactor, which comprises a supporting ring, a plurality of ring cavities formed in the longitudinal direction on the supporting ring, a plurality of vertical supporting structures arranged at the peripheral positions of the ring cavities, each vertical supporting structure comprising a plurality of vertical supporting structures, any vertical supporting structure comprising a support arranged at the peripheral position of the corresponding ring cavity of the supporting ring and a lug used for fixing a corresponding device in the half-pool type loop nuclear power reactor, the lug being mounted on the support to arrange the corresponding device in the corresponding ring cavity, and a plurality of positioning structures distributed below the supporting ring to horizontally fix the supporting ring on a concrete foundation. The supporting system can realize the supporting function of a main container, a main heat exchanger and a main pump and ensure the levelness of the main container, the main heat exchanger and the main pump.