Elution method for reserved plutonium in PUREX process dirty solvent

An elution method and solvent technology, applied in the field of radioactive waste treatment, can solve the problems of increased degradation products, failure to return to process reuse, and unsatisfactory results, achieving good application prospects and good elution effects

Active Publication Date: 2020-10-30
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

Since the plutonium content, degradation product content, and total radioactive content all exceed the standard, this high plutonium-retained contaminated solvent can neither be discharged to the waste liquid treatment unit, nor can it be returned to the process for reuse
What's more serious is that as the storage time increases, due to the effects

Method used

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  • Elution method for reserved plutonium in PUREX process dirty solvent
  • Elution method for reserved plutonium in PUREX process dirty solvent
  • Elution method for reserved plutonium in PUREX process dirty solvent

Examples

Experimental program
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Effect test

Embodiment 1

[0025] The 2BW material liquid obtained from a thermal experiment in the PUREX process technology research of China Institute of Atomic Energy is used as the processing object. The feed solution is the polluted solvent with excessive plutonium content obtained from the plutonium purification cycle. During the test, dilute acid solution, tetravalent uranium solution, N,N-dimethylhydroxylamine solution and sodium carbonate solution were used to elute plutonium. Its main chemical composition is: 30% (volume percentage) tributyl phosphate (TBP) and 70% (volume percentage) hydrogenated kerosene, in which plutonium content is 0.057g / L, nitric acid content is 0.03mol / L, dibutyl phosphate The content of ester acid (DBP) is 0.90×10 -3 mol / L, monobutyl phosphate (MBP) content is 2.30×10 -4 mol / L, the contents of other degradation products and metal ions were not determined. Before this experiment, the material solution had been placed for more than 4 years, and its appearance was a ye...

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Abstract

The invention belongs to the technical field of radioactive waste treatment, and relates to an elution method for reserved plutonium in a PUREX process dirty solvent. The elution method comprises thestep of adding a solution containing glutaryl imide dioxime, tetramethylammonium hydroxide and NaOH into the dirty solvent for treatment. By utilizing the elution method for reserved plutonium in thePUREX process dirty solvent, plutonium can be better eluted and recovered from the PUREX process dirty solvent.

Description

technical field [0001] The invention belongs to the technical field of radioactive waste treatment, and relates to a method for eluting plutonium retained in a PUREX process polluted solvent. Background technique [0002] The PUREX (Plutonium Uranium Reduction Extraction) process is currently the only commercial spent fuel reprocessing process. The main purpose of this process is to extract unburned or newly generated fuel (usually uranium and plutonium) from spent fuel, and at the same time separate some useful nuclides (such as neptunium-237, which is used for the production of plutonium-238, etc.). The process is a multi-cycle solvent extraction process, the aqueous phase is nitric acid solution containing metal ions, the organic phase extractant is tributyl phosphate (TBP), and the diluent is chemically inert hydrogenated kerosene, hydrogenated tetrapropylene (TPH) or normal dodecane etc. [0003] In this process, TBP-kerosene-HNO 3 The system will undergo chemical an...

Claims

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Application Information

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IPC IPC(8): G21F9/06G21F9/12G21F9/00C22B60/04C22B7/00
CPCG21F9/12G21F9/06G21F9/007C22B60/04C22B7/006Y02P10/20Y02W30/50Y02E30/30
Inventor 杨素亮杨志红朱礼洋柳倩田国新周今
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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