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A method for directly separating rare earth elements in uranium dioxide or spent fuel

A technology of uranium dioxide and rare earth elements, which is applied in chemical instruments and methods, reactor fuel elements, chemical/physical processes, etc., can solve problems such as high pollution and complex process flow, and achieve high economic benefits and simple and acceptable process operation. The effect of mature control and industrial application technology

Active Publication Date: 2020-01-24
INST OF MODERN PHYSICS CHINESE ACADEMY OF SCI +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

In the previous research and application of ionic liquids in the reprocessing of spent fuel, researchers have tried their best to dissolve spent fuel in ionic liquids and then separate related elements, which will inevitably lead to complicated process and more pollution.[ Patent CN103778983 B A method for directly dissolving uranium dioxide or spent fuel oxides by ionic liquid, Chu Taiwei, Yao Aining

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0027] Embodiment 1 A method for directly separating rare earth elements in uranium dioxide or spent fuel, comprising the following steps:

[0028] ⑴ Place the simulated spent fuel in the functionalized ionic liquid [Hbet][NTf 2 ], make it evenly mixed to obtain a solid mixed liquid.

[0029] Among them: simulated spent fuel refers to the Nd that will contain 4.97% Nd in any proportion 2 o 3 with UO 2 The powder mixture was uniformly mixed, and then heated in a high-temperature tube furnace at 700 °C and 4% H 2 - The mixture powder obtained after reduction in Ar atmosphere for 4 hours.

[0030] (2) Dissolve the solid mixture at 85°C for 40 minutes with a magnetic stirring speed of 1000 rpm, and centrifuge to obtain the supernatant and the undissolved uranium dioxide solid or undissolved spent fuel in the lower layer.

[0031] (3) Use ICP-OES to measure the metal ion content in the supernatant, and then calculate the Nd 2 o 3 with UO 2 The dissolution rates in ionic liq...

Embodiment 2

[0033] Embodiment 2 A method for directly separating rare earth elements in uranium dioxide or spent fuel, comprising the following steps:

[0034] ⑴ Place the simulated spent fuel in the functionalized ionic liquid [Hbet][NTf 2 ], make it evenly mixed to obtain a solid mixed liquid.

[0035] Among them: simulated spent fuel refers to the Nd that will contain 4.97% Nd in any proportion 2 o 3 with UO2 The mixture powder was mixed evenly, and then heated in a high-temperature tube furnace at 1200 °C and 4% H 2 - The mixture powder obtained after reduction in Ar atmosphere for 4 hours.

[0036] (2) Dissolve the solid mixture at 35°C with an ultrasonic power of 100W for 60 minutes, and centrifuge to obtain the supernatant and the undissolved uranium dioxide solid or undissolved spent fuel in the lower layer.

[0037] (3) Use ICP-OES to measure the metal ion content in the supernatant, and then calculate the Nd 2 o 3 with UO 2 The dissolution rates in ionic liquids are 99.89...

Embodiment 3

[0039] Embodiment 3 A method for directly separating rare earth elements in uranium dioxide or spent fuel, comprising the following steps:

[0040] (1) Put the simulated spent fuel in the functionalized ionic liquid 1-carboxymethyl-3-methylimidazolium bis(trifluoromethanesulfonyl)imide at a mass volume ratio (mg / mL) of 1:0.03, so that Mix evenly to obtain a solid mixed liquid.

[0041] Among them: simulated spent fuel refers to the Nd that will contain 2% Nd in any proportion 2 o 3 with UO 2 The powder mixture was uniformly mixed, and then heated in a high-temperature tube furnace at 700 °C and 4% H 2 - The mixture powder obtained after reduction in Ar atmosphere for 4 hours.

[0042] (2) Dissolve the solid mixture at 40°C with an ultrasonic power of 100W for 180 minutes, and centrifuge to obtain the supernatant and the undissolved uranium dioxide solid or undissolved spent fuel in the lower layer.

[0043] (3) Use ICP-OES to measure the metal ion content in the supernata...

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Abstract

The invention relates to a method for directly separating rare earth elements in uranium dioxide or spent fuel, the method comprising the following steps: (1) placing simulated spent fuel in a functionalized ionic liquid, and mixing it uniformly to obtain a solid mixed liquid; (2) placing The solid mixture is stirred and dissolved, and centrifuged to obtain the supernatant and the undissolved uranium dioxide solid or undissolved spent fuel in the lower layer; (3) the metal ion content in the supernatant is measured by ICP-OES, Then calculate the content of the rare earth compound or other fission products dissolved in the ionic liquid; (4) directly perform reprocessing of spent fuel elements on the lower uranium dioxide solid or undissolved spent fuel. The invention has the characteristics of simple process, easy operation, good economy, and environmental protection, and can be used for the removal of rare earth compounds (neutron poisons) in spent fuel reprocessing, including some fission products with large fission yield, and is suitable for industrial applications .

Description

technical field [0001] The invention relates to the technical field of nuclear fuel cycle and spent fuel reprocessing, in particular to a method for directly separating rare earth elements in uranium dioxide or spent fuel in an anhydrous and acid-free system. Background technique [0002] Safe and efficient development of nuclear power generation is a strategic choice to solve future energy supply and ensure sustainable economic and social development. Spent fuel contains a large amount of radioactive elements, 96% of which is the remaining unreacted uranium. The oxide fuel is uranium dioxide UO 2 form; about 1% of its mass is long-lived transuranic elements produced by beta decay after neutron capture by uranium-238. These transuranic elements are represented by AnO 2 (An=Pu, Np, Am) in the form of spent fuel; and 3% are some fission products (such as I, Xe, Sr, Ba, rare earth elements) [Rodney C. Ewing. Long-term storage of spent nuclear fuel . Nature materials, 2015, 14...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C19/50G21C21/00B01F11/02B01F13/08
CPCG21C19/50G21C21/00B01F31/80B01F33/45Y02E30/30
Inventor 范芳丽秦芝詹文龙杨帆赵志钢
Owner INST OF MODERN PHYSICS CHINESE ACADEMY OF SCI
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