Failed fuel assemblies repair technology after irradiation

A fuel assembly and damage technology, applied in the direction of reactor fuel elements, nuclear engineering, reactors, etc., can solve the problems of time-consuming, labor-intensive, high risk, and inconvenient operation, and achieve the effect of convenient use, simple tool structure, and low cost

Active Publication Date: 2011-11-09
QINSHAN NUCLEAR POWER
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AI Technical Summary

Problems solved by technology

[0006] In addition, reflective mirrors and telescopes are used to monitor and confirm the operation underwater. This operation is inconvenient, the underwater observation is not very clear, and the means for monitoring and confirming the underwater operation are insufficient; The Lissajous graph of the defect signal cannot be stored and recorded, and the signal curve can only be recorded by the paper recorder. The signal cannot be played back, and there is a disadvantage that the defect signal cannot be stored, recorded and analyzed. To review the defect, it is necessary to repeatedly pull out the fuel rod. This is not only time-consuming and labor-intensive, but also likely to cause damage to the rigid protrusions of the fuel single rod and the spacer grid, and the risk is great

Method used

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  • Failed fuel assemblies repair technology after irradiation
  • Failed fuel assemblies repair technology after irradiation
  • Failed fuel assemblies repair technology after irradiation

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Embodiment Construction

[0039] The present invention will be described in detail below in conjunction with the accompanying drawings and embodiments.

[0040] The flowchart of the damaged fuel assembly repair method after irradiation of the present invention, such as figure 1 As shown, the process flow is:

[0041] (1) Fuel assemblies whose fuel rods are confirmed to be damaged by sipping inspection, and fuel assemblies whose spacer grid coamings are confirmed to be damaged by underwater TV visual inspection;

[0042] (2) When the fuel rod is damaged and the spacer grid coaming is not damaged, turn the damaged component to be repaired 180°, remove the lower pipe seat, conduct eddy current inspection of the fuel rod, replace the damaged fuel rod, and assemble the lower pipe seat, Turn the repaired fuel assembly over 180°, conduct re-inspection of sipping and underwater TV appearance, and return to stacking for use after passing the inspection;

[0043] (3) When the fuel rods are damaged and the dam...

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Abstract

This invention provides a repairing technology for radiated damaged fuel components and its special equipment, which utilizes the current correction method for tilting baskets, the restoration correction device of 2-D pilot vanes and check to special location lattice correction gauge to correct the location lattices of slight damage of boarding and distortion and warp of few pilot vanes, and applies a method for exchanging positions of fuel bars in step for the framework replacement of heavily damaged boarding to expand the original bar replacement and repairing function and guarantees that old and new components will not be distorted because of no-bar framework.

Description

technical field [0001] The invention relates to a rod replacement and repair method and tool for damaged fuel assemblies after irradiation in a pressurized water reactor nuclear power plant, in particular to a post-irradiation damaged fuel assembly repair process for replacing and repairing damaged fuel rods and positioning grid coaming plates . Background technique [0002] During the refueling process of nuclear power plants, it is sometimes found that the reusable fuel rods are damaged and the fuel assembly positioning grid coamings are damaged to varying degrees. Both refueling and overhaul schedules have a significant impact. Leakage of damaged fuel rods will lead to the leakage of radioactive fission products into the primary circuit coolant, resulting in an increase in the radioactive level of the system and unnecessary radiation doses for the staff. In principle, the damaged fuel assemblies are not allowed to re-enter the reactor considering the risk control of oper...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C19/00G21C19/26
CPCY02E30/30
Inventor 李卓群薛新才郑宏练胡忠良王瑞正朱金华陈景佩许永军
Owner QINSHAN NUCLEAR POWER
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