Uranium (U) and plutonium (Pu) separation technology in Purex process

A process and process technology, applied in the field of nuclear fuel reprocessing, can solve the problems of unspecified process conditions and inapplicable actual operation process, etc., and achieve the effect of not being easy to acidolysis, strong complexation ability, and strong reduction ability

Active Publication Date: 2013-12-18
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
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Problems solved by technology

[0004] published "Reduction Kinetics of Formaldoxime and Pu(IV)" in Volume 44, No. 2, "Nuclear Chemistry and Radiation Chemistry" in 2010 and No. 2010 "Formaldoxime and HNO2 Redox Reaction Kinetics" published in Volume 32, Issue 1 of "Nuclear Chemistry and Radiation Chemistry" respectively discloses the relations

Method used

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  • Uranium (U) and plutonium (Pu) separation technology in Purex process

Examples

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Embodiment 1

[0017] Example 2

[0018] Identical with the method used in embodiment 1, difference is process condition, and process condition used and corresponding result are as table 2:

Embodiment 2

[0020] Example 3

[0021] Identical with the method used in embodiment 1, difference is process condition, and process condition used and corresponding result are as table 3:

Embodiment 3

[0023]

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Abstract

The invention belongs to the technical field of nuclear fuel postprocessing, and discloses a uranium (U) and plutonium (Pu) separation technology in a Purex process. According to the uranium and plutonium separation technology, Pu (IV) in 1BF material flow is reduced to Pu (III) in 1B tank by use of reducing agent 1BX and supplement extractant 1BS to enable plutonium to get into an aqueous phase and uranium to be retained in an organic phase, and uranium and plutonium separation is realized. The reducing agent 1BX which is used comprises 0.1-0.2 mol/L of formaldoxime, 0.35-0.5 mol/L of NO<3-> and 0.35-0.5 mol/L of H<+>; the flow ratio of 1BF:1BX is 1-4, and the flow ratio of 1BF:1BS is 4-6. The uranium and plutonium separation technology has the characteristics that the plutonium recovery rate is high, and the purification coefficients of removal of plutonium from uranium and removal of uranium from plutonium are large.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, and in particular relates to a process for separating uranium and plutonium in the Purex process. Background technique [0002] The separation of uranium and plutonium is an important process in the Purex process. Its main task is to use a reducing agent to convert the Pu(IV) Reduction to Pu(Ⅲ), which is extremely difficult to be extracted, makes plutonium enter the water phase while uranium remains in the organic phase, realizing the separation of uranium and plutonium. Because organic chemical reagents have the characteristics of fast reaction speed, good selectivity, no introduction of salt, and easy destruction, a lot of research has been carried out in the application of uranium and plutonium separation. Among them, N, N-dimethylhydroxylamine, N, N-ethyl hydroxyethyl hydroxylamine, hydroxyurea, acetohydroxamic acid, etc. can be used as reducing agents in the separation of ...

Claims

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Application Information

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IPC IPC(8): C22B60/02C22B60/04G21F9/06B01D11/04
Inventor 肖松涛刘协春罗方祥杨贺兰天孟照凯
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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