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Method for treating retained plutonium in waste organic phase in PUREX process

An organic phase and process technology, which is applied in the field of plutonium retention in the waste organic phase of the PUREX process, can solve the problems of difficult elution of uranium and plutonium, increased degradation products, and lack of competitiveness.

Pending Publication Date: 2022-07-26
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
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  • Claims
  • Application Information

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Problems solved by technology

However, the similar coordination ability of U(IV) and Pu(IV) makes U(IV) not fully competitive when replacing Pu(IV), which eventually leads to a large amount of U(IV) and a small amount of Pu(IV) being simultaneously Retained in the organic phase, forming a waste organic phase with uranium and plutonium content, degradation products and total radioactive content exceeding the standard
This spent organic phase can neither be discharged to waste liquid treatment unit nor returned to process reuse
What's more serious is that as the storage time increases, due to the effects of irradiation, metal ions, acid catalysis, etc., the degradation products in the waste organic phase will further increase, and at the same time, some U(IV) will be oxidized to U(VI), resulting in The composition of the spent organic phase is more complex, and the elution of retained uranium and plutonium is more difficult

Method used

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  • Method for treating retained plutonium in waste organic phase in PUREX process

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Embodiment 1

[0049] The waste organic phase feed liquid obtained from the PUREX process in China's nuclear fuel reprocessing pilot plant is taken as the treatment object. The feed liquid is the waste organic phase with excess plutonium content obtained by post-processing uranium-plutonium separation and plutonium purification cycle, and the plutonium elution operation is carried out with dilute acid solution and tetravalent uranium solution respectively. Its main chemical composition is: 30% (volume percent) tributyl phosphate (TBP) and 70% (volume percent) hydrogenated kerosene, of which the plutonium content is 0.06g / L, the uranium content is 4.5g / L, and the nitric acid content is 0.3mol / L. The content of dibutyl phosphate (DBP) determined by anion chromatography is 0.9mmol / L, and the content of monobutyl phosphate (MBP) is 0.23mmol / L. According to the concentration of retained plutonium and uranium in the waste organic phase, the actual concentration of MBP may be inferred. Above 1 mmo...

Embodiment 2

[0056] The treatment method of this embodiment is the same as that of embodiment 1, except that the concentration of the NaOH solution in step (2) is 2M; the measurement results are shown in Table 1.

Embodiment 3

[0058] The treatment method of this embodiment is the same as that of embodiment 1, the difference is that the volume ratio of the waste organic phase and the water phase extraction liquid is 5:1 (other conditions are the same).

[0059] Table 1

[0060]

[0061] According to Table 1, DPA concentration and NaNO 2 When the concentrations are all the same, the increase of heating time is beneficial to the stripping of plutonium. After the heating time is greater than 45min, the stripping rate of Pu(IV) reaches equilibrium; on the premise that the two phases are still acidic, the residual acid in the organic phase The higher the neutralization percentage, the higher the Pu(IV) stripping rate.

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Abstract

The invention relates to a method for treating retained plutonium in a PUREX process waste organic phase, the PUREX process waste organic phase contains an organic solvent, plutonium and tetravalent uranium, the method comprises the following steps: contacting the PUREX process waste organic phase with an aqueous phase reverse extraction liquid containing 2, 6-dipicolinic acid, and carrying out reverse extraction to obtain a reverse extraction product; in the PUREX process waste organic phase, the weight content of the tetravalent uranium is 100-1000 times of the weight content of the plutonium, the aqueous phase reverse extraction liquid further contains an oxidizing agent, and the oxidizing agent can oxidize the tetravalent uranium into hexavalent uranium. The plutonium elution method disclosed by the invention has a relatively good application prospect in the aspects of elution and recovery of retained plutonium in a high-plutonium retained waste organic phase of a spent fuel reprocessing plant.

Description

technical field [0001] The present disclosure relates to the technical field of radioactive waste liquid treatment, in particular, to a method for treating retained plutonium in the waste organic phase of the PUREX process. Background technique [0002] In order to make full use of uranium resources and reduce the volume of high-level radioactive waste to achieve sustainable development of nuclear energy, spent fuel needs to be reprocessed. 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 the unburned uranium and newly generated plutonium from the spent fuel, and to separate some useful nuclides (such as The raw material for the production of plutonium-238 is neptunium-237, etc.). This process is a multi-cycle solvent extraction process, the extraction agent used is tributyl phosphate (TBP), the diluent is chemically inert hydrogenated kerosene, hydroge...

Claims

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Application Information

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IPC IPC(8): C22B60/04C22B7/00
CPCC22B60/04C22B7/005
Inventor 朱礼洋柳倩郝轩周今田国新杨素亮吴远珊赵爱张国果曾巧巧薛勇陈勤牟凌
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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