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Plutonium purification cycle process using formaldoxime as back extraction reagent

The technology of stripping reagent and formaldehyde oxime is applied in the field of plutonium purification and circulation process, which can solve the problems of low concentration level and poor safety, and achieve the effects of reducing the amount of use, high plutonium yield and improving economy.

Active Publication Date: 2016-08-31
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] In order to solve the problems of low plutonium concentration level and poor security in the existing Purex process plutonium purification cycle using salt-free reducing reagents, taking into account the plutonium concentration effect and process safety, the invention provides a stripping reagent using formaldehyde oxime plutonium purification recycling process

Method used

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  • Plutonium purification cycle process using formaldoxime as back extraction reagent

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Embodiment 1

[0020] Applying the plutonium purification cycle process of the present invention to the purification and concentration of plutonium products in the Purex process, the following process conditions are adopted:

[0021] (1) The formaldehyde oxime concentration of 2BX is 0.6mol / L, and the nitric acid concentration is 0.4mol / L;

[0022] (2) The plutonium nitrate concentration of 2BF is 12g / L, the nitric acid concentration is 0.2mol / L, and the uranium concentration is 0.76g / L;

[0023] (3) The nitric acid concentration of 2BS is 0.2mol / L;

[0024] (4) flow ratio 2BF:2BX=5:1;

[0025] (5) There are 11 stages of back-extraction and 5 stages of re-extraction.

[0026] The plutonium concentration of the obtained plutonium product liquid is 60.3g / L, the residual plutonium concentration in the organic phase is about 0.4mg / L, the plutonium yield is greater than 99.99%, and the separation factor SF for removing uranium from plutonium is U / Pu >10 4 .

Embodiment 2

[0028] Applying the plutonium purification cycle process of the present invention to the purification and concentration of plutonium products in the Purex process, the following process conditions are adopted:

[0029] (1) The formaldehyde oxime concentration of 2BX is 0.5mol / L, and the nitric acid concentration is 0.5mol / L;

[0030] (2) The plutonium nitrate concentration of 2BF is 15g / L, the nitric acid concentration is 0.15mol / L, and the uranium concentration is 1.86g / L;

[0031] (3) The nitric acid concentration of 2BS is 0.3mol / L;

[0032] (4) flow ratio 2BF:2BX=3:1;

[0033] (5) There are 12 stages of back extraction and 3 stages of re-extraction.

[0034] The plutonium concentration of the obtained plutonium product liquid is 54.8g / L, the residual plutonium concentration in the organic phase is about 0.5mg / L, the plutonium yield is greater than 99.99%, and the separation factor SF for removing uranium from plutonium is U / Pu >3000.

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Abstract

Belonging to the field of nuclear fuel reprocessing, the invention provides a plutonium purification cycle process using formaldoxime as a back extraction reagent to solve the problems of low plutonium concentration level, poor safety and the like in existing Purex process plutonium purification cycle adopting a salt-free reduction reagent. The process includes: a 2BX's formaldoxime concentration of 0.5-0.7mol / L, a 2BF's nitric acid concentration of 0.15-0.3mol / L, a 2BX's nitric acid concentration of 0.1-0.5mol / L, a flow ratio 2BF:2BX of 3-5:1, a back extraction level of more than 10, and a supplement extraction level of 3-5. The plutonium purification cycle process provided by the invention can realize plutonium concentration by more than 5 times during back extraction, the obtained plutonium product liquid has a plutonium concentration up to 60g / L, a high plutonium yield and good uranium removal effect can be achieved. Within a technological condition range, the process has good operation stability, and has good economical efficiency.

Description

technical field [0001] The invention belongs to the field of nuclear fuel reprocessing, in particular to a plutonium purification cycle process using formaldehyde oxime as a stripping reagent. Background technique [0002] The Purex process is currently the main process used in reprocessing plants, which includes a co-decontamination cycle, a uranium purification cycle and a plutonium purification cycle. Among them, the purpose of the plutonium purification cycle is to purify and concentrate the crude plutonium products obtained from the co-decontamination cycle through extraction and stripping processes, and finally obtain qualified plutonium products. figure 1 . [0003] In order to ensure the plutonium yield of the entire reprocessing process, it is generally required that the plutonium yield of the plutonium purification cycle must reach 99.9%. Since the plutonium purification cycle has the characteristics of high concentration of plutonium in the organic phase (above ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/50G21F9/12C22B7/00C22B60/04
CPCC22B7/006C22B60/04G21C19/50G21F9/12Y02E30/30Y02P10/20
Inventor 肖松涛刘协春罗方祥李丽杨贺兰天
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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