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Preparation method of quadrivalent uranium-cerium-oxygen solid solution

A solid solution and solution technology, which is applied in the field of preparing tetravalent uranium-cerium-oxygen, can solve the problem that it is difficult to ensure the uniformity of U-Pu-O solid solution, and achieve the effect of ensuring safety and operability

Inactive Publication Date: 2010-08-18
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This method is difficult to ensure the uniformity of the U-Pu-O solid solution, so many countries have successively studied how to improve the uniformity of the distribution of uranium and plutonium in the MOX fuel produced by the mechanical mixing method

Method used

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  • Preparation method of quadrivalent uranium-cerium-oxygen solid solution
  • Preparation method of quadrivalent uranium-cerium-oxygen solid solution

Examples

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Embodiment 1

[0023] Dissolve uranium oxide with 6mol / L nitric acid, configure 65g / L uranyl nitrate solution, dissolve cerous nitrate and oxalic acid respectively with deionized water, prepare 0.5mol / L cerous nitrate solution and 0.5mol / L oxalic acid solution, and 65g / L uranyl nitrate solution is placed in the cathode chamber of the electrolytic cell, 2.5mol / L nitric acid is added into the anode chamber, the titanium mesh is used as the cathode, and the platinum-plated titanium sheet is used as the anode. -2 . Carry out electrolysis at normal temperature, after 15 hours, get uranium nitrate solution at the cathode, draw out the cathode chamber electrolyte; press UO 2 : CeO 2 The weight ratio is calculated as 90:10, add 0.5mol / L cerous nitrate solution, mix well, slowly add into 0.5mol / L oxalic acid solution, filter the obtained precipitate and wash with deionized water, dry naturally, place in In the tube furnace, the temperature was raised to 1223K, and kept for 4 hours, then cooled natu...

Embodiment 2

[0025] Dissolve uranium oxide with 6mol / L nitric acid, configure 180g / L uranyl nitrate solution, dissolve cerous nitrate and oxalic acid respectively with deionized water, and prepare 0.5mol / L cerous nitrate solution and 0.5mol / L oxalic acid solution; 180g / L uranyl nitrate solution is placed in the cathode chamber of the electrolytic cell, 2.5mol / L nitric acid is added to the anode chamber, the titanium mesh is used as the cathode, and the platinum-plated titanium sheet is used as the anode. -2 . Perform electrolysis at normal temperature, after 8 hours, get uranium nitrate solution at the cathode, press UO 2 : CeO 2 Calculated at a weight ratio of 95:5, add 0.5 mol / L cerous nitrate solution, mix well, slowly add to 0.5 mol / L oxalic acid solution, filter the resulting precipitate and wash with deionized water, dry naturally, and place In the tube furnace, the temperature was raised to 1473K, and kept for 2 hours, then cooled naturally, and finally the oxide was obtained. fi...

Embodiment 3

[0027] Dissolve uranium oxide with 6mol / L nitric acid, configure 150g / L uranyl nitrate solution, dissolve cerous nitrate and oxalic acid respectively with deionized water, and prepare 0.5mol / L cerous nitrate solution and 0.5mol / L oxalic acid solution; 150g / L uranyl nitrate solution is placed in the cathode chamber of the electrolytic cell, 3mol / L nitric acid is added into the anode chamber, the titanium mesh is used as the cathode, the platinum-plated titanium sheet is used as the anode, the area ratio of yin and yang is 2, and the current density is 20mA.cm -2 . Carry out electrolysis at normal temperature, after 30 hours, the cathode will get uranium nitrate solution, draw out the cathode chamber electrolyte, press UO 2 : CeO 2 Calculated at a weight ratio of 99:1, add 0.5 mol / L cerous nitrate solution, mix well, slowly add to 0.5 mol / L oxalic acid solution, filter the resulting precipitate and wash with deionized water, dry naturally, place in In the tube furnace, the tem...

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Abstract

The invention relates to a preparation method of a quadrivalent uranium-cerium-oxygen solid solution, wherein uranium nitrate is prepared by an electrolytic reduction method, and the quadrivalent uranium-cerium-oxygen solid solution is prepared by adopting a coprecipitation method; the method comprises the following steps: using a uranyl nitrate solution as a cathode electrolyte, using a nitric acid solution as an anode electrolyte, using a platinum-plated titanium electrode as an anode, and using a titanium net as a cathode; electrolyzing under the condition that the current density is 20 to 80 mA.cm-2 to obtain a uranium nitrate solution; then adopting the coprecipitation method, using oxalic acid as a precipitator, adding a mixed solution of the uranium nitrate and cerous nitrate obtained through electrolytic reduction, and coprecipitating to obtain a uranium-cerium oxalate deposit; and finally calcining at the temperature of 1173 to 1473K under argon protection to obtain the quadrivalent uranium-cerium-oxygen solid solution. The invention avoids leading reductive gas under the condition of high temperature, and the quadrivalent uranium-cerium-oxygen solid solution is prepared under a milder condition.

Description

technical field [0001] The invention relates to the preparation of tetravalent uranium-cerium-oxygen solid solution, in particular to a method for preparing tetravalent uranium-cerium-oxygen based on uranium nitrate solution obtained by electrolytic reduction. Background technique [0002] Dissolution of spent fuel is an essential part of spent fuel reprocessing. How to simulate the dissolution process of spent fuel core is an important content in the study of spent fuel dissolution. Uranium oxide alone (UO 2 ) is easily dissolved in nitric acid medium, but plutonium oxide (PuO 2 ) is difficult to dissolve in nitric acid solution. If a small amount of HF is added to concentrated nitric acid solution, PuO 2 can be dissolved, but F - The presence of ions has strong corrosion on the dissolver. If PuO 2 and UO 2 A solid solution is formed, which is easily dissolved by nitric acid solution. [0003] In the related research of uranium-plutonium mixed oxide (MOX) fuel, due...

Claims

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Application Information

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IPC IPC(8): G21F9/30C01G43/025C01F17/00
Inventor 文明芬段五华朱礼洋陈靖王建晨
Owner TSINGHUA UNIV
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