Probe for ultrasonic inspection of pressurized water reactor fuel assembly and manufacturing process thereof

Abstract

The invention belongs to the technical field of nuclear power station before-service and in-service inspection, and in particular, relates to a probe for ultrasonic inspection of a pressurized water reactor fuel assembly and a manufacturing process thereof. The probe comprises a probe bracket and ultrasonic probe monomers; the probe bracket comprises a base plate, wire leading grooves, a socket mounting seat and probe mounting holes, the base plate is provided with the wire leading grooves and the probe mounting holes, and is connected with the socket mounting seat through screws; the probe bracket can be provided with two ultrasonic probe monomers simultaneously; the ultrasonic probe monomers are mounted in the probe mounting holes, and outgoing cables of the ultrasonic probe monomers are connected with the socket mounting seat through the wire leading grooves; the ultrasonic probe monomers comprise two ultrasonic probe monomer units arranged at intervals, and each ultrasonic probe monomer unit comprises a probe wafer, a sound insulation material, a backing filler and a back reflection inhibition layer from front to back sequentially; wires are arranged on and below the wafer. The height size of the probe produced by the process can be controlled to be within 1.2 mm, and the probe can be guaranteed to be safely close to a fuel rod.

Description

technical field [0001] The invention belongs to the technical field of pre-service and in-service inspection and other non-destructive testing of nuclear power plants, and particularly relates to a probe used for ultrasonic inspection of pressurized water reactor fuel assemblies and a manufacturing process thereof. Background technique [0002] The PWR fuel assembly is composed of fuel rods and a skeleton. The fuel rods are supported and clamped in the skeleton in a regular arrangement. Among them, the role of the fuel rod cladding is to ensure the mechanical strength of the fuel rod, and at the same time contain the nuclear fuel and its fission products, forming the first barrier between the strongly reflective fission products and the external environment. During the operation of the reactor, due to the long-term high temperature and high irradiation conditions of the fuel rods, the irradiation swelling of the fuel pellets may cause cladding creep and lead to cladding dama...

AI Technical Summary

Problems solved by technology

During the operation of the reactor, due to the long-term high-temperature and high-irradiation conditions of the fuel rods, the radiation swelling of the fuel pellets may cause cladding creep and cause cladding damage, resulting in leakage of highly reflective fission products

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