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Method for determining content of impurity elements in uranium nitride solid sample

A technology of impurity elements and determination methods, applied in the field of chemical detection

Pending Publication Date: 2020-06-19
CHINA NORTH NUCLEAR FUEL
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Research on the preparation process and performance of uranium nitride fuel has not been systematically carried out in China, so the chemical research on uranium nitride is particularly important

Method used

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  • Method for determining content of impurity elements in uranium nitride solid sample
  • Method for determining content of impurity elements in uranium nitride solid sample
  • Method for determining content of impurity elements in uranium nitride solid sample

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0055] 1 sample dissolved

[0056] Weigh 1.0g of sample, place the sample in a 150mL quartz beaker, add 5mL of concentrated nitric acid solution, heat and dissolve on a temperature-adjusted electric heating plate at 230°C to 260°C, after the sample is completely dissolved, evaporate it to a small amount at low temperature, and take Next, cool to room temperature.

[0057] 2 Separation of uranium matrix

[0058] Use 5.5mol / L nitric acid solution as the medium, wash the beaker three times, and transfer the sample to the quartz separatory funnel that has been added with 20mL uranium extraction reagent. Shake the separatory funnel for 30 seconds and let it stand for 10 minutes. Place the lower clear liquid in a well-balanced reversed-phase chromatography separation column. Use a 10mL quartz volumetric flask to receive the eluent to the mark, dilute to volume, and shake well for testing.

[0059] 3 Preparation of standard solution

[0060] Preliminary determination of each eleme...

Embodiment 2

[0084] 1 sample dissolved

[0085] Weigh 1.0g of sample, place the sample in a 150mL quartz beaker, add 7.5mL of concentrated nitric acid solution, heat and dissolve on a temperature-adjusting electric heating plate at 230°C to 260°C, and after the sample is completely dissolved, evaporate it to a small amount at low temperature. Remove and cool to room temperature.

[0086] 2 Separation of uranium matrix

[0087] Using 8mol / L nitric acid solution as the medium, wash the beaker three times, and transfer the sample to a quartz separatory funnel that has been added with 30mL uranium extraction reagent. Shake the separatory funnel for 30 seconds and let it stand for 10 minutes. Place the lower clear liquid in a well-balanced reversed-phase chromatography separation column. Use a 10mL quartz volumetric flask to receive the eluent to the mark, dilute to volume, and shake well for testing.

[0088] 3 Preparation of standard solution

[0089] Preliminary determination of each elem...

Embodiment 3

[0112] 1 sample dissolved

[0113] Weigh 1.0g of sample, place the sample in a 150mL quartz beaker, add 10mL of concentrated nitric acid solution, heat and dissolve on a temperature-adjusting electric heating plate at 230°C to 260°C, and after the sample is completely dissolved, evaporate it to a small amount at low temperature, and take Next, cool to room temperature.

[0114] 2 Separation of uranium matrix

[0115] Use 10mol / L nitric acid solution as the medium, wash the beaker three times, and transfer the sample to the quartz separatory funnel that has been added with 40mL uranium extraction reagent. Shake the separatory funnel for 30 seconds and let it stand for 10 minutes. Place the lower clear liquid in a well-balanced reversed-phase chromatography separation column. Use a 10mL quartz volumetric flask to receive the eluent to the mark, dilute to volume, and shake well for testing.

[0116] 3 Preparation of standard solution

[0117] Preliminary determination of each ...

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Abstract

The invention relates to a method for determining the content of impurity elements in a uranium nitride solid sample. The method comprises the following steps: step 1, dissolving a sample; weighing 1.0 g of a sample, putting the sample into a 150 mL quartz beaker, adding 5-10 mL of a concentrated nitric acid solution, heating and dissolving the sample, after the sample is completely dissolved, evaporating the sample to 2-3 mL at a low temperature, taking down the sample, and cooling the sample to room temperature; 2, separating a uranium matrix; separating a uranium matrix in the sample by adopting an extraction method-reversed phase chromatographic separation column method; step 3, determination of a sample; iCP-AES (Inductively Coupled Plasma-Atomic Emission Spectrometry) is adopted, andthe sample from which the uranium matrix is separated is determined by a standard curve method. The invention successfully establishes a method for determining the content of impurity elements in uranium nitride powder or pellet by plasma emission spectrometry. The content of impurity elements can be accurately determined by utilizing the experimental conditions listed in the content of the invention, accurate detection data is reported, a method is provided for related detection of uranium nitride in the future, and special production is effectively matched.

Description

technical field [0001] The invention belongs to the field of chemical detection, and in particular relates to a method for determining the content of impurity elements in a uranium nitride solid sample. Background technique [0002] Uranium nitride has good electrical conductivity and metallic properties, and can react with various metals at high temperatures. In the atmospheric environment, a certain thickness of oxide layer will be formed on the surface, thereby preventing the oxidation reaction from proceeding. Therefore, uranium nitride in the atmospheric environment is stable. Is a potential power reactor nuclear fuel element. [0003] Foreign research and development on uranium nitride fuel used in space nuclear power plants has reached the engineering application stage in the late 1990s. In addition, in the planning of the fourth-generation nuclear energy system in the world, uranium nitride fuel has been used as an important candidate fuel for two types of reactors...

Claims

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Application Information

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IPC IPC(8): G01N21/73G01N1/28G01N1/44
CPCG01N21/73G01N1/28G01N1/44
Inventor 马妍琳代燕赵竹霞张洪伟
Owner CHINA NORTH NUCLEAR FUEL
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