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Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow

A process and process technology, applied in the field of nuclear fuel reprocessing, can solve problems such as unsuitable for purification and recovery, unfavorable material liquid follow-up treatment, etc.

Active Publication Date: 2013-09-18
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, due to the many types of redox agents used, it is not conducive to the subsequent treatment of the feed liquid, and sodium nitrite is selected as the reducing agent, which is also a salty reducing agent that is not expected to be used in the post-treatment, so it is not suitable for purification. and recycled neptunium

Method used

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  • Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow
  • Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow
  • Process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow

Examples

Experimental program
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Effect test

Embodiment 1

[0029] The experimental bench is installed in the glove box, and the neptunium in the plutonium extraction tank raffinate 2AW and the uranium extraction tank raffinate 2DW feed liquid is recovered and purified, and the operation steps are as follows:

[0030] (1) After the plutonium extraction tank raffinate 2AW and the uranium extraction tank raffinate 2DW are evaporated and concentrated, sodium metavanadate is used as the oxidant seasoning, and 5mol / L HNO 3 Adjust the acidity to obtain 2NAF, the feed liquid to be purified, in which 2NAF contains Np, U, Pu and fragment elements, and Np mainly exists in the form of Np(Ⅵ);

[0031] (2) Introduce 2NAF into neptunium extraction tank 2NA, and introduce 30% TBP-kerosene (volume fraction) into 2NA as extractant 2NAX, 3mol / L HNO 3 As a detergent 2NAS, in which U, Np, and Pu are co-extracted into the organic phase 2NAP, and the split elements enter into the aqueous phase 2NAW, and the flow ratio of 2NAX:2NAF:2NAS is 1:3:1.

[0032] (...

Embodiment 2

[0041] The operation steps and method are the same as in Example 1, except that the parameters such as seasoning concentration and reducing agent concentration change, as shown in the following table:

[0042] Table 1 parameter list

[0043]

Embodiment 3

[0045] The operation steps and methods are the same as those in Example 1, except that the seasoning parameters and oxalic acid concentration in step (4) of the second purification process are specifically 3NBP with 5mol / L HNO 3 , 0.6 mol / L hydrazine seasoning, add 1.0 mol / L oxalic acid and make the oxalic acid excess 0.1 mol / L, carry out oxalate precipitation, the recovery rate of neptunium is 99.91%.

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Abstract

The invention belongs to the technical field of nuclear fuel reprocessing and discloses a process for recovering and purifying neptunium from waste liquor discharged from 2AW+2DW in Purex flow. The process comprises the primary neptunium purification process and the secondary neptunium purification process; the process comprises the following steps: by taking 30 volume percent of TBP-kerosene as an extraction agent, extracting Np, U and Pu to the organic phase, and allowing the fission fragments to enter the aqueous phase; adding a reducing agent and an extraction agent into the organic phase, reversely extracting the Np to the aqueous phase; further extracting uranium and plutonium, and performing oxalate precipitation, filtering and calcining on the obtained aqueous phase product to obtain the purified neptunium oxide solid. The process has the advantages that the neptunium recovery rate is over 98 percent, and the uranium and plutonium removal coefficient in neptunium is high.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel reprocessing, and in particular relates to a process for recovering and purifying neptunium from 2AW+2DW waste liquid of the Purex process. Background technique [0002] The neptunium content in spent fuel is about 500-700 g / t, of which 237 The irradiation product of Np is 238 Pu is an important source of α radiation and has a wide range of uses. At present, there are basically two ways to extract neptunium from high-level waste liquid and medium-level waste liquid in reprocessing plants. The main techniques for extracting neptunium are ion exchange method and solvent extraction method. The principle of the ion exchange method is to use the different affinity between neptunium, plutonium, splinter elements and ion exchange resin under the condition of high concentration nitric acid to realize the separation of neptunium, plutonium and splinter elements; and then use reagents such as ferrous...

Claims

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Application Information

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IPC IPC(8): C22B7/00C22B3/26C02F1/26C02F1/62G21F9/06C22B60/02
CPCY02P10/20
Inventor 叶国安何辉唐洪彬蒋德祥李峰峰朱礼洋朱文彬常利黄小红袁洁琼刘占元林如山李高亮张虎
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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