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Fused salt system for dry post-treatment of oxide spent fuel

A technology for spent fuel and oxides, which is applied in the fields of reactor fuel elements, greenhouse gas reduction, recycling technology, etc., and can solve problems such as difficulty in achieving satisfactory yields

Active Publication Date: 2012-10-17
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Nevertheless, the yield of plutonium is still difficult to meet the satisfactory target

Method used

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  • Fused salt system for dry post-treatment of oxide spent fuel

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0020] Using UF 4 , add LiF and UF 5 , to improve the temperature and melting characteristics of the molten salt system, with UO 2 As raw material, metal uranium is directly electrolytically deposited.

[0021] The specific operation process is:

[0022] 1) Prepare a suitable molten salt. Take UF 4 and UF 5 128g and 0.13g each.

[0023] 2) Control the temperature at 600-650°C to melt the molten salt in the crucible.

[0024] 3) Add 3.84g LiF.

[0025] 4) Add 6.60g of UO 2 .

[0026] 5) When the salt melts, stir the melt with a stainless steel bar, then take the supernatant to analyze UO 2 solubility. After the sampling is completed, CV scanning is carried out, and constant potential deposition is carried out according to the information obtained from the CV scanning. The results showed that potentiostatic deposition gave dendritic deposits on stainless steel cathodes.

Embodiment 2

[0028] Using UF 4 , add UF 4 A mixture of perfluorinated and LiF to UO 2 As raw material, metal uranium is directly electrolytically deposited.

[0029] The specific operation process is:

[0030] 1) Prepare a suitable molten salt. Take UF 4 and UF 4 100g and 5g each of the perfluorinated mixture.

[0031] 2) Control the temperature at 650-700°C to melt the molten salt in the crucible.

[0032] 3) Add 1.58g LiF.

[0033] 4) Add 5.33g UO 2 .

[0034] 5) When the salt melts, stir the melt with a stainless steel bar, then take the supernatant to analyze UO 2 solubility. After the sampling is completed, CV scanning is carried out, and constant potential deposition is carried out according to the information obtained from the CV scanning. The results showed that potentiostatic deposition gave dendritic deposits on stainless steel cathodes.

Embodiment 3

[0036] Using UF 4 , add LiF and UF 5 , with UO 2 As raw material, metal uranium is directly electrolytically deposited.

[0037] The specific operation process is:

[0038] 1) Prepare a suitable molten salt. Take UF 4 and UF 5 80g and 8g each.

[0039] 2) Control the temperature at 600-650°C to melt the molten salt in the crucible.

[0040] 3) Add 0.09g LiF.

[0041] 4) Add 4.84g UO 2 .

[0042] 5) When the salt melts, stir the melt with a stainless steel bar, then take the supernatant to analyze UO 2 solubility. After the sampling is completed, CV scanning is carried out, and constant potential deposition is carried out according to the information obtained from the CV scanning. The results showed that potentiostatic deposition gave dendritic deposits on stainless steel cathodes.

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Abstract

The invention discloses a fused salt system for the dry post-treatment of an oxide spent fuel. In the fused salt system, uranium tetrafluoride is used as a fused salt main body, and a perfluoride mixture of uranium pentafluoride or uranium tetrafluoride, which occupies 0.1-10 percent of the total mass of the fused salt, is added. The fused salt system not only can be used for dissolving the oxidespent fuel in the fused salt, but also can avoid strong complex anions in the fused salt from seriously corroding equipment.

Description

technical field [0001] The invention belongs to the technical field of non-aqueous solution reprocessing flow for irradiated fuel assemblies, and in particular relates to a molten salt system for dry reprocessing of oxide spent fuel. Background technique [0002] The dry post-processing technology was developed by ANL in the United States and RIAR and RICT in Russia. Russia has carried out dry electrolytic reprocessing with several kilograms of oxidized spent fuel, proving that the technology is feasible in principle. The laboratory scale-up experiment of dry electrolytic reprocessing of spent metal fuel in the United States has also been successful. Currently, the molten salt process is one of the four most active dry reprocessing technologies. The principle is to use complex anion salts with strong complexing properties for uranium and plutonium, such as Cl - , F - , SO 4 2- After melting, the spent fuel is melted in this molten salt, and the elements to be processed...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C25C3/34G21C19/48
CPCY02E30/30Y02W30/50
Inventor 欧阳应根王长水刘利生常尚文常利何虎郭建华李瑞雪高巍高繁星叶国安
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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