Process for purifying zirconium in Purex flow plutonium purification cycle

A purification process, plutonium purification technology, which is applied in the field of zirconium purification process in the Purex process plutonium purification cycle, and can solve the problems of increased difficulty in purification of trace Zr

Active Publication Date: 2014-08-27
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Therefore, the difficulty of purifying trace Zr in ...

Method used

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  • Process for purifying zirconium in Purex flow plutonium purification cycle

Examples

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Embodiment 1

[0022] At a temperature of 25°C, a mixing chamber with a volume of 12ml and a clarification chamber of 18ml was used as the 2A extraction tank, and the ratio of the organic phase to the aqueous phase was about 2:1 to simulate a plutonium purification cycle. The composition of the 2AF feed liquid is: 6.28g / L of Pu 4+ , 0.74g / L of UO2 2+ , 3.5mol / L of HNO 3 and 0.3073mg / L of Zr (add U target to facilitate the analysis of Zr); 2AX is 30% TBP-kerosene; 2AS is nitric acid with a concentration of 0.8mol / L; the residence time of the feed liquid in the mixing chamber is 1min, and the extraction grade The number is 8, the number of washing stages is 7, and the flow ratio of 2AF:2AX:2AS is 4:1:0.45.

[0023] During the experiment, the tank was first filled with the feed solution not containing uranium, plutonium and zirconium for two hours, and then the feed solution containing uranium, plutonium and zirconium was added. After running for 5.0 hours, an instant sample was taken every 2...

Embodiment 2

[0032] Same as the method and steps used in Example 1, the difference is that the concentration of nitric acid in the 2AF feed liquid is 3.7mol / L, and 2AS is the nitric acid of 0.85mol / L for the concentration; the extraction stages of the extraction section are 10 grades, and the The number of washing stages is 8; the flow ratio of 2AF:2AX is 6.

[0033] The thermal test results of the plutonium purification cycle bench show that the Pu yield is 99.97%, and the purification factor of Zr is 159.

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Abstract

The invention belongs to the technical field of spent fuel post-treatment, and discloses a process for purifying zirconium in a Purex flow plutonium purification cycle. 30% tri-butyl-phosphate (TBP)-kerosene is adopted as an extraction agent 2AX in a 2A extractor, so as to recover uranium and plutonium and purify fission fragments. The process comprises an extraction section and a washing section; and the concentration of a nitric acid in a 2AF feed liquid is 3.5-3.7mol/L, and 2AS is an HNO3 solution of which the concentration is 0.8-0.85mol/L. The process has the advantages that the plutonium yield is greater than 99.9%, and the purification coefficient of zirconium is greater than 100.

Description

technical field [0001] The invention belongs to the technical field of spent fuel reprocessing, and in particular relates to a zirconium purification process in the plutonium purification cycle of the Purex process. Background technique [0002] Spent fuel refers to the nuclear fuel that is unloaded from the reactor after the irradiation reaches the specific burnup of the planned unloading in the nuclear reactor, and is no longer used in the reactor. The process of chemically treating it to remove impurities such as fission products and recover fissile nuclides and convertible nuclides and some other usable substances is called spent fuel reprocessing. At present, the spent fuel reprocessing process in various countries mainly adopts the Purex process or its improved process. It mainly includes three cycles of co-decontamination and separation cycle, plutonium purification cycle and uranium purification cycle. [0003] Among the fission products of spent fuel, zirconium (Z...

Claims

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Application Information

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IPC IPC(8): C22B60/04C22B3/38
Inventor 肖松涛罗方祥刘协春杨贺兰天孟照凯
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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