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Zirconium Matrix Removal Process and Burnup Measurement Method Using the Process

A measurement method and matrix technology, applied in nuclear engineering, greenhouse gas reduction, climate sustainability, etc., can solve problems such as data deviation from the true value, failure of burnup measurement, affecting the separation effect of uranium and burnup monitoring body, etc. The effect of widespread application and promotion of value

Active Publication Date: 2021-01-05
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0009] The purpose of the present invention is to provide a zirconium matrix removal process and a burnup measurement method using the process, so as to solve the problem that a large amount of zirconium matrix in the nuclear fuel solution makes the liquid phase The separation column of the chromatogram is saturated, which seriously affects the separation effect of uranium and the burnup monitor in the subsequent separation process of the uranium and the burnup monitor, which leads to the failure of the burnup measurement or the deviation of the data from the true value

Method used

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  • Zirconium Matrix Removal Process and Burnup Measurement Method Using the Process
  • Zirconium Matrix Removal Process and Burnup Measurement Method Using the Process
  • Zirconium Matrix Removal Process and Burnup Measurement Method Using the Process

Examples

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Effect test

Embodiment 1

[0065]Such asfigure 2 The shown burnup measurement method using the zirconium matrix removal process includes a sample cutting and fractionation step, a sample dissolution step, a hydrofluoric acid removal step, a separation step of uranium and a burnup monitoring body, and a determination step for the content of uranium and burnup monitoring body It also includes a zirconium matrix removal step, the zirconium matrix removal step is located between the hydrofluoric acid removal step and the uranium and burnup monitoring body separation step; the solution obtained through the zirconium matrix removal step can be directly used for uranium and burnup monitoring Body separation step.

[0066]Through the zirconium matrix removal process, the burnup measurement process provided by the present invention can remove a large amount of zirconium matrix in the solution after the hydrofluoric acid removal step, so that the zirconium content in the solution is lower than the subsequent uranium and b...

Embodiment 2

[0068]On the basis of Example 1, the zirconium matrix removal step includes the following steps:

[0069](A) Adjusting the dissolving solution system, adjusting the dissolving solution Y1 obtained in the hydrofluoric acid removal step to obtain the dissolving solution Y2 from which the zirconium matrix is ​​to be removed;

[0070](B) Extract the zirconium matrix in the dissolving liquid Y2 with the extractant solution to obtain the dissolving liquid Y3.

[0071]Wherein, the step (A) includes the following steps:

[0072](A1) Precipitating metal ions, adding ammonia to the solution Y1 to precipitate the metal ions in the solution Y1;

[0073](A2) Filter the dissolved solution Y1 to obtain the metal ion precipitate generated in step (A1);

[0074](A3) The precipitate is dissolved, and the precipitate obtained by filtering in the step (A2) is dissolved with nitric acid to obtain a dissolving liquid Y2.

[0075]Since the solution obtained after the hydrofluoric acid removal step is a mixed acid system of ni...

Embodiment 3

[0081]On the basis of embodiment 2, step (B) includes the following steps:

[0082](B1) Put the extractant solution and the dissolving liquid Y2 together in the reaction vessel, stirring and extracting the zirconium matrix in the dissolving liquid Y2;

[0083](B2) Let stand, discard the upper organic phase, and the lower aqueous phase is the dissolved liquid Y3, which can be directly used in the separation step of uranium and burnup monitoring body.

[0084]Wherein, in step (B1), the extraction temperature is 20-30°C, and the extraction time is 10-30 min.

[0085]After the extraction and stirring, take out the reaction vessel from the water bath and let it stand for 2 to 5 minutes, then discard the upper organic phase, which contains the zirconium matrix; the lower aqueous phase is the dissolving liquid Y3, which contains low zirconium content At 0.1g / L, it can be directly used in the separation process of uranium and burnup monitoring body for subsequent burnup measurement.

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Abstract

The invention discloses a zirconium substrate removal process and a burnup measurement method using the process. The burnup measurement method includes a sample cutting and separation step, a sample dissolution step, a hydrofluoric acid removal step, a separation step of uranium and a burnup monitoring body, and The step of determining the content of uranium and burnup monitoring body; further including the step of removing zirconium matrix, the step of removing zirconium matrix is ​​located between the step of removing hydrofluoric acid and the step of separating uranium and burnup monitoring body; the solution obtained through the step of removing zirconium matrix It can be directly used in the separation step of uranium and burnup monitoring body. Through the zirconium matrix removal process, the burnup measurement process provided by the present invention can remove a large amount of zirconium matrix in the solution after the hydrofluoric acid removal step, so that the zirconium content in the solution is lower than the subsequent separation steps of uranium and burnup monitoring body requirements, and then the burnup measurement process can accurately measure the burnup value of the special system of zirconium-based dispersed nuclear fuel elements, which has wide application and promotion value.

Description

Technical field[0001]The invention relates to a method for measuring burnup of fuel elements, in particular to a process for removing a zirconium matrix and a method for measuring burnup using the process.Background technique[0002]Burnup is an indicator of the degree of fissile nuclide consumption of nuclear fuel elements after a chain fission reaction occurs in the reactor, and an indicative parameter of the degree of nuclear fuel irradiation and energy release. As one of the most important performance indicators of nuclear fuel elements, the accuracy of burnup measurement is of great significance to the development of new nuclear fuel elements and the determination of refueling intervals.[0003]The burnup measurement of nuclear fuel elements usually includes the monitoring volume method and the heavy isotope measurement method. The relevant isotope abundance or activity is measured by isotope mass spectrometry or energy spectroscopy, and the burnup value is calculated. Many measure...

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 苏冬萍梁帮宏陈云明张劲松李兵李顺涛孙鹏冯伟伟
Owner NUCLEAR POWER INSTITUTE OF CHINA
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