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A method for identification of damaged fuel assemblies

A fuel assembly and identification method technology, applied in the direction of reducing greenhouse gases, climate sustainability, reactors, etc., can solve problems such as irregular changes, increased unloading time, and fuel assembly damage, so as to improve identification accuracy and efficiency , The effect of saving unloading time

Active Publication Date: 2019-09-17
CNNC FUJIAN FUQING NUCLEAR POWER
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Therefore, when the online sip device or the gripper of the loading and unloading machine is contaminated by radioactive substances, due to 133 The γ count rate of Xe is much higher than the background count rate, and the irregular change will interfere with the judgment of whether the fuel assembly is damaged, causing a large number of undamaged components to be treated as suspected damaged components
Increased the cost of subsequent offline sipping, the radiation dose of personnel, increased unloading time, and delayed the main line of nuclear power plant overhaul

Method used

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  • A method for identification of damaged fuel assemblies
  • A method for identification of damaged fuel assemblies
  • A method for identification of damaged fuel assemblies

Examples

Experimental program
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Effect test

example 1

[0055] Example 1: Count rate of an unbroken component as a function of time without contamination of the in-line sip device or loader gripper as figure 2 As shown, the probability distribution diagram of the corresponding count rate is shown as image 3 shown.

example 2

[0056] Example 2: Count rate of an unbroken component as a function of time with contamination of an in-line sip device or loader gripper as Figure 4 As shown, the probability distribution diagram of the corresponding count rate is shown as Figure 5 shown.

example 3

[0057] Example 3: The count rate of a broken component varies with time as Image 6 (YQF04G) and Figure 7 (YQF04G) shown. The probability distribution of the corresponding count rate is as follows Figure 8 (YQF04G) and Figure 9 (YQF04G) shown.

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Abstract

The invention belongs to the technical field of nuclear fuel management at a nuclear power plant, and concretely relates to a damaged fuel assembly identification method. By taking regard of a workingphysical mechanism of an on-line sipping apparatus, and according to the on-line sipping apparatus, change of data with time and a statistical frequency spectrum can be measured, so that whether a fuel assembly is damaged or not can be determined. The method is used for effectively increasing the accuracy for the fuel on-line sipping suspected damaged assembly, fuel on-line sipping inspection efficiency is increased, and discharging time is saved.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel management in nuclear power plants, and in particular relates to a method for identifying damaged fuel assemblies. Background technique [0002] In the field of nuclear fuel management in nuclear power plants, such as figure 1 As shown, when the reactor is refueled, the fuel assembly is lifted out of the core with the gripper of the loading and unloading machine. When it rises to the upper position of the fixed sleeve, due to the reduction of the external pressure on the fuel assembly, if the fuel rod is damaged, accelerates the fission gas 133 Xe leaks outward. The compressed air flow blown from the blowing port at the bottom of the fixed sleeve carries the leaked fission gas up to the water surface in the sleeve, and the suction port located here sucks the air entrained with the fission gas into the metering tank, and the suction is used to generate vacuum It is realized by gas injection...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/10
CPCG21C17/10Y02E30/30
Inventor 孟凡锋耿飞张鹏蔡光明
Owner CNNC FUJIAN FUQING NUCLEAR POWER