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Method for separating element palladium and sub-actinide elements from high-level waste

A technology for high-level radioactive waste and minor actinides, applied in separation methods, chemical instruments and methods, solid adsorbent liquid separation, etc., to achieve safe and effective treatment and disposal, high selectivity, simple and efficient methods

Inactive Publication Date: 2014-01-15
ZHEJIANG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0008] The safe treatment and disposal of high-level radioactive waste is one of the key links in nuclear fuel cycle technology. There is no report on the efficient separation of palladium and minor actinides from high-level radioactive waste at the same time in the prior art

Method used

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  • Method for separating element palladium and sub-actinide elements from high-level waste
  • Method for separating element palladium and sub-actinide elements from high-level waste
  • Method for separating element palladium and sub-actinide elements from high-level waste

Examples

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Embodiment 1

[0039] The preparation of embodiment 1 adsorbent

[0040] Dissolve 100 grams of 2,6-bis-(5,6-di-n-butyl-1,2,4-triazin-3-yl)-pyridine in 1000 mL of dichloromethane and mix well; add 300 grams of coating polymer macroporous SiO 2 (SiO 2 -P) Stir evenly to volatilize most of the dichloromethane until the material is in a nearly dry state, and then vacuum-dry the nearly dry material at 45° C. for 24 hours.

Embodiment 2

[0041] The preparation of embodiment 2 adsorbent

[0042] Dissolve 100 g of 2,6-bis-(5,6-dimethyl-1,2,4-triazin-3-yl)-pyridine in 1500 mL of dichloromethane and mix well; add 600 g of coating polymer macroporous SiO 2 (SiO 2 -P) Stir evenly to volatilize most of the dichloromethane until the material is in a nearly dry state, and then vacuum-dry the nearly dry material at 45° C. for 24 hours.

Embodiment 3

[0043] Example 3 Preparation of Adsorbent

[0044] Dissolve 100 grams of 2,6-bis-(5,6-diethyl-1,2,4-triazin-3-yl)-pyridine in 3000 mL of dichloromethane and mix well; add 1500 grams of coating polymer macroporous SiO 2 (SiO 2 -P) Stir evenly to volatilize most of the dichloromethane until the material is in a nearly dry state, and then vacuum-dry the nearly dry material at 45° C. for 24 hours.

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Abstract

The invention discloses a method for separating element palladium from high-level waste, which includes the steps: adding concentrated nitric acid into nitrate solution of the high-level waste to adjust the nitric acid concentration to be 2mol / L; and allowing the high-level waste nitrate solution with the nitric acid concentration adjusted to pass through a chromatographic column filled with adsorbent to enable element palladium and sub-actinide elements to be adsorbed by the chromatographic column filled with the adsorbent; using nitric acid aqueous solution of thiourea to elute the chromatographic column with the adsorbed element palladium and sub-actinide elements, and eluting the element palladium out in a nitrate form, wherein the thiourea concentration of the nitric acid aqueous solution of thiourea is 0.2mol / L, and the nitric acid concentration is 0.1mol / L; and after the element palladium is eluted out in a nitrate form, using saltpeter solution with the pH (potential of hydrogen) being 6.5 to elute the chromatographic column with the adsorbed sub-actinide elements and eluting the sub-actinide elements out in a nitrate form. The method is simple, efficient, high in selectivity of the chromatographic column and effective in separation.

Description

technical field [0001] The invention relates to the field of reprocessing of high-level radioactive waste in the nuclear industry, in particular to a method for separating elemental palladium and minor actinides from high-level radioactive waste. Background technique [0002] As the high-level radioactive waste (HLLW) produced by spent fuel (SF) reprocessing, its safe treatment and disposal is one of the key links in nuclear fuel cycle technology. According to the national atomic energy development policy, rational and effective use of limited nuclear resources, ensuring safety, nuclear non-proliferation, environmental adaptability, economy, and effective disposal of HLLW through spent fuel reprocessing technology are its basic guidelines. [0003] Spent fuel contains fragmentation products (FP) such as exothermic elements and long-lived (millions of years) minor actinides (MA). All FP elements go into the HLLW. For long-lived MA, separation / transmutation technology has be...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B01D15/42B01J20/283G21F9/06C22B7/00
CPCY02P10/20
Inventor 张安运
Owner ZHEJIANG UNIV
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