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Analytical method of determining content of uranium in plutonium dioxide

A technology of plutonium dioxide and analysis method, applied in the field of analysis of uranium content in plutonium dioxide powder

Inactive Publication Date: 2013-05-15
THE 404 COMPANY LIMITED CHINA NAT NUCLEAR
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

At present, there is no relevant report on the determination of trace uranium in plutonium dioxide powder in China

Method used

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  • Analytical method of determining content of uranium in plutonium dioxide
  • Analytical method of determining content of uranium in plutonium dioxide

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0049] ① Weigh 9.0 mg of plutonium dioxide powder with a balance with a sensitivity of 0.1 mg;

[0050] ② Use steel-lined polytetrafluoroethylene sealed digestion tank (outside temperature: 150°C), use 8mol / LHNO 3 -0.06mol / LHF mixed acid heating to dissolve plutonium dioxide powder;

[0051] ③Heat (outer surface temperature of steel-lined polytetrafluoroethylene sealed digestion tank: 150°C) to concentrate the solution volume to 0.5mL-1.0mL, add 2mL of HNO with a concentration of 2moL / L 3 , continue heating (outside temperature of steel-lined polytetrafluoroethylene sealed digestion tank: 150°C) and concentrate to 0.5mL-1.0mL, add 2mL of HNO with a concentration of 2moL / L again 3 ;

[0052] ④ Add dropwise 0.05mL of 30% (w / w) hydrogen peroxide to adjust the plutonium valence state under the condition that the outer surface temperature of the steel-lined polytetrafluoroethylene sealed digestion vessel is 60°C;

[0053] ⑤Transfer the solution into a 5mL volumetric flask, and u...

Embodiment 2

[0058] ① Weigh 9.0 mg of plutonium dioxide powder with a balance with a sensitivity of 0.1 mg;

[0059] ② Use steel-lined polytetrafluoroethylene sealed digestion tank (outside temperature: 155°C), use 9mol / LHNO 3 -0.07mol / LHF mixed acid heating to dissolve plutonium dioxide powder;

[0060] ③Heat (outer surface temperature of steel-lined polytetrafluoroethylene sealed digestion tank: 155°C) to concentrate the solution volume to 0.5mL-1.0mL, add 2.5mL of HNO with a concentration of 2.5moL / L 3 , continue heating (outside temperature of steel-lined polytetrafluoroethylene sealed digestion tank: 155°C) and concentrate to 0.5mL-1.0mL, add 2.5mL of HNO with a concentration of 2.5moL / L again 3 ;

[0061]④ Add dropwise 0.05mL of 30% (w / w) hydrogen peroxide to adjust the valence state of plutonium under the condition that the outer surface temperature of the steel-lined polytetrafluoroethylene sealed digestion vessel is 65°C;

[0062] ⑤Transfer the solution into a 5mL volumetric fl...

Embodiment 3

[0067] ① Weigh 10.0 mg of plutonium dioxide powder with a balance with a sensitivity of 0.1 mg;

[0068] ② Use steel-lined polytetrafluoroethylene sealed digestion tank (outside temperature: 155°C), use 10mol / LHNO 3 -0.08mol / LHF mixed acid heating to dissolve plutonium dioxide powder;

[0069] ③Heat (outer surface temperature of steel-lined PTFE-sealed digestion tank: 155°C) to concentrate the solution to a volume of 0.5mL-1.0mL, and add 2.5mL of HNO with a concentration of 3.0moL / L 3 , continue heating (outside temperature of steel-lined polytetrafluoroethylene sealed digestion tank: 155°C) and concentrate to 0.5mL-1.0mL, add 2.5mL of HNO with a concentration of 3.0moL / L again 3 ;

[0070] ④ Add dropwise 0.05mL of 30% (w / w) hydrogen peroxide to adjust the valence state of plutonium under the condition that the outer surface temperature of the steel-lined polytetrafluoroethylene sealed digestion vessel is 65°C;

[0071] ⑤Transfer the solution into a 5mL volumetric flask, an...

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Abstract

The invention belongs to the field of analysis technique on the content of uranium in plutonium dioxide powder, and particularly relates to an analytical method of determining the content of uranium in plutonium dioxide, aiming at accurately determining the content of uranium in plutonium dioxide powder. The analytical method comprises the following steps: sampling, dissolving, concentrating, adjusting plutonium valence state, conducting constant volume, extracting the plutonium element, and determining the uranium content. According to the analytical method, the separation of uranium from the plutonium element can be realized through utilizing extraction separation, the uranium content in the separated solution can be determined, the precision on determining the content of uranium in plutonium dioxide powder is more than 10%, and the additional recovery rate can achieve 86.0%-107.5%.

Description

technical field [0001] The invention belongs to the technical field of uranium content analysis in plutonium dioxide powder. Background technique [0002] The uranium content in plutonium dioxide powder is a key parameter to investigate the deuranium effect of plutonium in the reprocessing process. In order to accurately determine the uranium content in plutonium dioxide powder, it is necessary to eliminate the interference of plutonium elements on the determination of uranium content (in plutonium dioxide powder The plutonium content is greater than or equal to 86.0%). At present, there is no relevant report on the determination technology of trace uranium in plutonium dioxide powder in China. Contents of the invention [0003] The purpose of the invention is to accurately measure the uranium content in plutonium dioxide powder. [0004] The present invention is an analysis method for measuring uranium content in plutonium dioxide powder, comprising the following steps:...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G01N1/28G01N1/40G01N1/44
Inventor 曹希彭龙牟凌马精德姜国杜蒋军清鹿东峰吉头杰吉永超张军红李秀娟晁余涛
Owner THE 404 COMPANY LIMITED CHINA NAT NUCLEAR