On-site preparation method of a neutron flux measuring tube power station

A technology for on-site preparation and flux measurement, applied in the field of maintenance of nuclear power plants, can solve the problems of reducing the strength and pressure resistance of the end of the neutron flux tube, and achieve the effect of ensuring the quality of preparation, the yield of finished products, and the sealing performance.

Active Publication Date: 2021-11-12
CNNC NUCLEAR POWER OPERATION MANAGEMENT +1
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Problems solved by technology

[0005] During the first installation of the neutron flux tube and during the replacement of the neutron flux tube within the lifetime of the nuclear reactor, it is necessary to cut, form and process the end of the finger sleeve. The preparation process requires high precision, otherwise it may be Resulting in reduced strength and pressure resistance at the end of the neutron flux tube

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  • On-site preparation method of a neutron flux measuring tube power station

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Embodiment Construction

[0019] The present invention is described in detail below in conjunction with accompanying drawing and specific embodiment:

[0020] Use the profile bracket purchased on the market as the preparation bracket and storage bracket for the neutron flux tube, store the spare parts of the neutron flux measurement tube on the bracket, and measure the neutron flux tube with a grade 1E tape measure According to the preparation requirements, a margin of 2 mm is left on the neutron flux tube, and a common tube cutter is used to cut off the length. After the assembly of the pipe beveling machine is completed, use the beveling machine to verify the beveling of the pipes of the same size, model and material. The stub end of the flux tube is beveled for welding. After the groove processing is completed, the bullet head is welded to the end of the neutron flux tube by argon arc welding. After cooling, use a reinforcement removal machine to remove the weld reinforcement. After the reinforcem...

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Abstract

The invention relates to the technical field of nuclear power plant maintenance, in particular to a neutron flux measuring tube power plant on-site preparation method. Use a grade 1E tape measure to measure the neutron flux tube. According to the preparation requirements, leave a margin of 2mm on the neutron flux tube before intercepting. After the assembly of the pipe beveling machine is completed, use the beveling machine to verify the beveling of the pipes of the same size, model and material. The stub end of the flux tube is beveled for welding. After the groove processing is completed, the bullet head is welded to the end of the neutron flux tube by argon arc welding. After cooling, use a reinforcement removal machine to remove the weld reinforcement. After the reinforcement is removed, ensure that the weld height is not lower than the base metal, and the surface finish is 1.6. Check with the general gauge, and store it in the preparation bracket after passing the leak test. This process can ensure that the technical conditions of the neutron flux tube to be installed meet the accuracy requirements.

Description

technical field [0001] The invention relates to the technical field of nuclear power plant maintenance, in particular to a neutron flux measuring tube power plant on-site preparation method. Background technique [0002] Reactor neutron flux tubes in pressurized water reactor nuclear power plants, commonly known as bushings, are one of the key equipment in pressurized water reactor nuclear power plants. The number of neutron flux tubes varies with the size of the reactor. The number of sub-flux tubes is 20-50. As a measurement channel for the neutron flux of the core nuclear measurement system, the neutron flux tubes are evenly distributed in the channel of the core fuel assembly, run through the fuel assembly, and are exposed in the core. The neutron flux tube is the pressure boundary of the primary circuit, because the mechanical wear caused by radiation embrittlement and flow-induced vibration will make the tube wall thinner or even damaged, which will cause leakage and ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B23P15/00G21C17/108
CPCB23P15/00G21C17/108Y02E30/30
Inventor 王成林戚宏昶付荣真费志松黄慧敏代巍巍罗飞华田亮陆少威周伟
Owner CNNC NUCLEAR POWER OPERATION MANAGEMENT
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