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Analysis method of fission gas

A fission gas and analysis method technology, applied in the field of nuclear fuel post-irradiation inspection, can solve problems such as fuel irradiation swelling, affecting the performance of fuel elements, threats to reactor safety operation, etc., and achieve the effect of simplifying the separation system

Inactive Publication Date: 2016-01-20
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0002] During the irradiation process of fuel, a large amount of fission products will be produced, and the accumulation of fission products will cause severe radiation swelling of the fuel, which will seriously affect the performance of fuel elements and pose a threat to the safe operation of the reactor.

Method used

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  • Analysis method of fission gas
  • Analysis method of fission gas

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Embodiment 1

[0033] Such as Figure 5 Shown, a kind of analysis method of fission gas, described analysis method is to adopt gas chromatograph to carry out component content analysis to sample fission gas, described analysis method comprises the following steps of carrying out in sequence:

[0034] a. Collect the fission gas and collect the above fission gas in the sampling container;

[0035] b. Use the fission gas extraction tool to extract a specific volume of fission gas from the above sampling container, and send the above specific volume of fission gas into a gas chromatograph for gas chromatographic analysis;

[0036] c. After completing the gas chromatographic analysis of step b, extract fission gas equivalent to the specified volume from the above sampling container, and send the extracted fission gas into a gas chromatograph for gas chromatographic analysis;

[0037] e, calculate the ratio of the target component amount in the specific volume of fission gas taken in the sampling...

Embodiment 2

[0045] This embodiment further defines or provides a specific implementation on the basis of the fuel assembly provided in Embodiment 1. In order to further verify the reliability of the previous two consecutive measurements, between steps c and e, multiple A sampling measurement step, the sampling measurement step is to repeatedly extract fission gas equivalent to the specified volume from the above sampling container more than once after the completion of step c, and perform gas chromatographic analysis on the fission gas extracted each time . If the ratio of the amount of the target component in the fission gas of the specific volume taken in the sampling container is equal or approximately equal to the ratio of the peak area of ​​the target component in the two gas chromatographic analysis results for two consecutive times in the multiple sampling measurement step, then it can be A reliable conclusion can be drawn from the previous measurement results, so that the peak are...

Embodiment 3

[0056] Such as figure 1 and figure 2 As mentioned above, this embodiment provides a specific chromatographic analysis method for a certain sample fission gas, the column temperature is 100°C; the inlet temperature is 120°C; the detector temperature is 140°C; the filament temperature is 220°C; helium is the carrier gas , purity ≥ 99.995%; carrier gas flow rate 30ml / min; reference gas flow rate 30ml / min; makeup gas flow rate 10ml / min; fission gas. Precisely measure 0.3 μL, 1.2 μL, 20 μL, 50 μL and 100 μL of krypton and xenon standard gases respectively, analyze according to the conditions, and use the injection volume V (μL) of the target gas to make a linear regression on the corresponding peak area S. The obtained sample analysis results are as follows figure 1 As shown, in the present embodiment, the continuous measurement method provided in Example 1 has been used for multiple measurements, and the obtained chromatogram overlay results are as follows figure 2 shown.

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Abstract

The invention discloses an analysis method of fission gas. According to the analysis method, a gas chromatograph is adopted for conducting component content analysis on the sample fission gas, the fission gas of specific volumes is extracted from a sampling container several times, the fission gas extracted every time is fed into the gas chromatograph for gas chromatography, the specific value of target component amounts in the fission gas, of the specific volumes, continuously extracted from the sampling container twice is calculated, the specific value of target component peak areas in two continuous gas chromatography results is calculated, and the numerical relationship between the two specific values is compared. According to the analysis method, a chromatographic separation method for the fission gas is established, the interference of air and especially nitrogen in the air in krypton in the measuring process is avoided through parallel optimization and operation control, and effective separation of krypton, xenon and other interfering components is achieved. The method is easy and convenient to operate, high in efficiency, stable and reliable, and the nitrogen and krypton separation effect is better than that of reported documents.

Description

technical field [0001] The invention belongs to the field of post-irradiation inspection of nuclear fuel, in particular to an analysis method for fission gas. Background technique [0002] During the irradiation process of fuel, a large amount of fission products will be produced, and the accumulation of fission products will cause serious radiation swelling of the fuel, which will seriously affect the performance of fuel elements and pose a threat to the safe operation of the reactor. Among them, the fission gases krypton and xenon have large fission yields and are gaseous, which have a great impact on fuel. It is very important to accurately measure the total content of krypton and xenon gases released from fuel elements to determine the xenon / krypton ratio, fission gas release rate, and the relationship with burnup. Different fuel pellets, different manufacturing processes, different burnup values ​​and different 235 The total amount of fission gas produced by U abundan...

Claims

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Application Information

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IPC IPC(8): G01N30/88
Inventor 罗宁陈云明张劲松曹其如
Owner NUCLEAR POWER INSTITUTE OF CHINA
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