Method for extracting and separating element palladium from high-level waste

A technology of high-level radioactive waste and elements, which is applied in the field of post-processing of high-level radioactive waste in the nuclear industry, can solve problems such as large-scale promotion, and achieve the effects of high selectivity, good separation effect, and simple operation

Inactive Publication Date: 2012-08-08
ZHEJIANG UNIV
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0008] However, using a chromatographic column to separate elemental palladium in the form of nitrate is suitable for small-scale implementation in the laboratory. Due to the limitation of the separation volume, it cannot be widely promoted in the industry. Therefore, it is necessary to develop The elemental palladium separation method that can realize large-scale application in industry

Method used

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  • Method for extracting and separating element palladium from high-level waste
  • Method for extracting and separating element palladium from high-level waste
  • Method for extracting and separating element palladium from high-level waste

Examples

Experimental program
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Effect test

Embodiment 1

[0043] (1) The high-level radioactive waste is made into a nitrate solution according to the process of the U.S. invention patent with the document number US6843921B2 and the secondary actinides are separated to obtain a nitrate solution containing metal elements such as Cs, Sr, Rh, Ru, Pd, etc. The total concentration of metal ions in the high-level waste nitrate solution is 10×10 -3 mol / L, adjust the concentration of nitric acid in the nitrate solution to 3mol / L with concentrated nitric acid;

[0044] (2) Mix 2,6-bis(5,6-dinonyl-1,2,4-triazin-3-yl)pyridine, octanol and dodecane to obtain solution B, 2,6-bis(5 ,6-Dinonyl-1,2,4-triazin-3-yl)pyridine concentration is 4×10 -2 mol / L, based on the total volume of octanol and dodecane, the volume fraction of octanol is 30%, and the volume fraction of dodecane is 70%;

[0045] (3) Mix the nitrate solution of high-level radioactive waste with a nitric acid concentration of 3mol / L and solution B in equal volumes, shake at 25°C for 90 minut...

Embodiment 2～7

[0050] Examples 2-7 are the same as the experimental conditions in Example 1, except that in step (1), the concentration of nitric acid in the nitrate solution is adjusted to 0.42mol / L, 1mol / L, 1.5mol with concentrated nitric acid. / L, 2.5mol / L, 4mol / L, 5.11mol / L.

[0051] See the attachment for the separation results figure 1 , figure 2 , image 3 .

[0052] Attached figure 1 , 2 , 3 It can be seen that with the difference of nitric acid concentration, the distribution ratio of metal ions (distribution ratio = equilibrium concentration of metal ions in the organic phase / equilibrium concentration of metal ions in the water phase) is also different, and the concentration of nitric acid is adjusted to At 3mol / L, the distribution ratio of Pd(II) reaches the maximum, continue to increase the concentration of nitric acid, and the distribution ratio of Pd(II) is a constant value.

Embodiment 8

[0054] (1) The high-level radioactive waste is made into a nitrate solution according to the process of the U.S. invention patent with the document number US6843921B2 and the secondary actinides are separated to obtain a nitrate solution containing metal elements such as Cs, Sr, Rh, Ru, Pd, etc. The total concentration of metal ions in the high-level waste nitrate solution is 10×10 -3 mol / L, adjust the concentration of nitric acid in the nitrate solution to 3mol / L with concentrated nitric acid;

[0055] (2) Mix 2,6-bis(5,6-dinonyl-1,2,4-triazin-3-yl)pyridine, hexanol and dodecane to obtain solution B, 2,6-bis(5 ,6-Dinonyl-1,2,4-triazin-3-yl)pyridine concentration is 4×10 -2 mol / L, based on the total volume of hexanol and dodecane, the volume fraction of hexanol is 30%, and the volume fraction of dodecane is 70%;

[0056] (3) Mix the nitrate solution of high-level radioactive waste with a nitric acid concentration of 3mol / L and solution B in equal volumes, shake at 25°C for 90 minut...

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Abstract

The invention discloses a method for extracting and separating element palladium from high-level waste. The method comprises the following steps of: adding concentrated nitric acid into nitrate solution of the high-level waste, from which minor actinide elements have been separated, to adjust the concentration of nitric acid to be 0.42-5.11 mol / L to obtain solution A; mixing 2,6-bi (5,6-dinonyl-1,2,4-triazine-3-yl) pyridine, R-OH and alkanes of C6-C12 to obtain solution B, wherein R is alkyl groups of C6-C12, and the volume fraction of R-OH is 30-100 percent in terms of the total volume of the R-OH and alkanes of C6-C12; mixing the solution A and the solution B, oscillating and then demixing to obtain an oil phase and a water phase; separating the oil phase from the water phase to obtain palladium nitrate-containing oil phase and the nitrate solution of the high-level waste from which the element palladium is separated respectively. The method for extracting and separating element palladium from high-level waste provided by the invention has the advantages of high selectivity, high separation capacity and suitability for large-scale industrial application.

Description

Technical field [0001] The invention relates to the field of post-treatment of high-level radioactive waste in the nuclear industry, and in particular to a method for extracting and separating elemental palladium from high-level radioactive waste. Background technique [0002] As high-level radioactive waste (HLLW) produced by the post-processing of spent fuel (SF), its safe treatment and disposal is one of the key aspects of nuclear fuel cycle technology. [0003] According to the national nuclear energy development policy, rational and effective utilization of limited nuclear resources, ensuring safety, nuclear non-proliferation, environmental adaptability, economic efficiency, and effective treatment and disposal of HLLW through spent fuel reprocessing technology are its basic policies. [0004] Spent fuel contains heat-generating elements and long-lived (millions of years) sub-actinides (MA) and other fragmented products (FP). The status of post-processing is: In addition to the ...

Claims

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Application Information

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IPC IPC(8): G21F9/06B01D11/04C22B11/00
Inventor 张安运
Owner ZHEJIANG UNIV
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