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Method for separating americium from curium

A separation method and separation membrane technology are applied in the field of americium curium separation, which can solve the problems of poor separation effect and affect the separation effect, and achieve the effect of enhancing applicability, ensuring separation effect, and avoiding contact reduction.

Active Publication Date: 2022-05-13
TSINGHUA UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] Based on this, the object of the present invention is to provide a method for separating americium and curium, which realizes the effective separation of Am / Cm based on the oxidation-sieving-extraction phase coupling system through ion configuration differences, and solves the problem of reducibility in the prior art. The organic phase affects the separation effect and leads to problems such as poor separation effect

Method used

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  • Method for separating americium from curium
  • Method for separating americium from curium
  • Method for separating americium from curium

Examples

Experimental program
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Effect test

Embodiment 1

[0036] N,N,N',N'-tetraoctyl-3-oxoglutaramide (TODGA) / n-dodecane separation of americium (Am) and curium (Cm).

[0037] The feed liquid area is 10mL containing 1×10 -7 mol / L Am, Cm (that is, both Am and Cm are 1×10 -7 mol / L), 1×10 -2 3mol / L HNO of mol / L sodium bismuthate 3 solution. The separation membrane is a graphene oxide membrane with the regulated interlayer spacing greater than the hydration radius of the curium ion and smaller than the hydration radius of the americium ion. Permeation zone includes 5mL of 3mol / L HNO 3 solution, and 5 mL of the organic phase of 0.1 mol / L N, N, N', N'-tetraoctyl-3-oxoglutaramide / n-dodecane solution.

[0038] The distribution ratio (distribution ratio, D) is defined as the ratio of the concentration of metal ions in the permeate side (organic phase + nitric acid aqueous solution) to the feed liquid area, and the separation factor (SF) is defined as the ratio of the distribution ratios of each ion.

[0039] After 12 hours of stirring,...

Embodiment 2

[0041] Trialkylphosphine (TRPO) / toluene separation of americium (Am) and curium (Cm).

[0042] The feed liquid area is 10mL containing 1×10 -7 mol / L Am, Cm, 1×10 -2 1mol / L HNO in mol / L potassium permanganate 3 solution. The separation membrane is a commercial reverse osmosis membrane whose interlayer spacing is greater than the hydration radius of curium ions and smaller than the hydration radius of americium ions, which is regulated by deionized water immersion. Permeation zone includes 5mL 1mol / LHNO 3 solution, 5mL of 1mol / L trialkylphosphine / toluene solution in the organic phase.

[0043] After 18 hours of stirring, the distribution ratio and separation factor of Am and Cm are as follows Figure 2b shown, from Figure 2b It can be clearly seen that the separation factor of Cm to Am is higher than 100, thereby realizing the separation of Am / Cm.

Embodiment 3

[0045] Di-(2-ethylhexyl)phosphoric acid (HDEHP) / n-octanol separation of americium (Am) and curium (Cm).

[0046] The feed liquid area is 10mL containing 1×10 -7 mol / L Am, Cm, 1×10 -2 0.01mol / L HNO in mol / L potassium dichromate 3 solution. The separation membrane is a commercial nanofiltration membrane whose interlayer distance obtained through drying treatment is larger than the hydration radius of the curium ion and smaller than the hydration radius of the americium ion. Permeation zone includes 5mL 0.01mol / L HNO 3 solution, 5 mL of 0.5 mol / L di-(2-ethylhexyl) phosphoric acid / n-octanol solution as the organic phase.

[0047] After 24 hours of stirring, the distribution ratio and separation factor of Am and Cm are as follows Figure 2c shown. from Figure 2c It can be clearly seen that the separation factor of Cm to Am is higher than 100, thereby realizing the separation of Am / Cm.

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Abstract

The invention discloses a method for separating americium from curium. The method comprises the following steps: oxidizing trivalent americium ions in a to-be-separated component into high-steric-hindrance americium acyl ions through an oxidizing agent in a feed liquid region, intercepting the americium acyl ions and the oxidizing agent in the feed liquid region by a separation membrane, continuously dispersing curium ions in the feed liquid region through the separation membrane into a permeation region, and extracting the curium ions into an organic phase through an extracting agent in the permeation region, an organic phase in the permeation region cannot permeate through the separation membrane to diffuse to the feed liquid region; the separation membrane separates the feed liquid area from the permeation area and has a function of screening non-steric hindrance and high steric hindrance ions; the feed liquid area is a nitric acid aqueous solution containing an oxidizing agent and to-be-separated americium and curium ions; and the permeation area comprises a nitric acid aqueous solution with the same acidity as the feed liquid area and an organic phase containing an extracting agent for extracting curium ions. According to the method, efficient and stable separation of americium and curium is achieved through ion configuration differences based on an oxidation-screening-extraction phase coupling system, and the problem that the separation effect is affected by a reductive organic phase in a conventional extraction separation method is solved.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel cycle and waste liquid treatment, in particular to a method for separating americium and curium. Background technique [0002] A large amount of spent fuel will be generated during the utilization of nuclear energy, and its effective disposal is one of the key factors to ensure the sustainable development of nuclear energy. At present, for the reprocessing of spent fuel, the "advanced nuclear fuel cycle" scheme is generally adopted in the world, that is, the actinide elements (Np, Am, Cm, etc.) Transformation into short-lived or stable nuclides. However, before the final transmutation of actinides, in order to increase the transmutation rate of actinides and further reduce the volume of α-radioactive waste, in addition to separating actinides from high-level waste liquid, it is also necessary to carry out actinide transmutation. Intragroup separation of (Am and Cm). This is due to the fact...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B60/02C22B3/22C22B3/26C22B3/44
CPCC22B60/0295C22B3/22C22B3/44
Inventor 王志鹏徐超陆跃翔陈靖
Owner TSINGHUA UNIV