Method for separating element Pd from high-level radioactive waste

A technology of high-level radioactive waste and elements, which is applied in the field of reprocessing of high-level radioactive waste in the nuclear industry, to achieve high selectivity, simple and efficient methods, and good separation effects

Inactive Publication Date: 2011-10-19
ZHEJIANG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] However, after the nitric acid solution of high-level waste is separated from the minor actinides, it also contains metal elements such as Cs, Sr, Rh, Ru, Pd, and the element Pd must also be separated. This patent does not involve Cs, Sr, Rh , Ru, Pd and other metal elements for further separation treatment, and Pd as a precious metal element, its separation treatment has broad market prospects

Method used

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  • Method for separating element Pd from high-level radioactive waste
  • Method for separating element Pd from high-level radioactive waste
  • Method for separating element Pd from high-level radioactive waste

Examples

Experimental program
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Embodiment 1

[0031] The preparation of embodiment 1 adsorbent

[0032] 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

[0033] The preparation of embodiment 2 adsorbent

[0034] 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

[0035] Example 3 Preparation of Adsorbent

[0036] 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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PUM

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Abstract

The invention discloses a method for separating an element Pd from the high-level radioactive waste, which comprises the following steps: (1) adding concentrated nitric acid in nitrate solution of the high-level radioactive waste which separates minor actinides for adjusting the concentration of the nitric acid to 1.7-2.3 mol / L; (2) leading the nitrate solution of the high-level radioactive wasteafter the adjustment of the concentration of the nitric acid to pass through a column filled with an absorbent, and leading the element Pd to be absorbed by the column filled with the absorbent; and (3) using nitric acid water solution of thiourea to elute the column filled with the element Pd, and eluting out the element Pd in the form of nitrate, wherein the concentration of the thiourea in thenitric acid water solution of the thiourea is 0.1-0.3 mol / L, and the concentration of the nitric acid is 0.05-0.15 mol / L. The method is simple and high-efficient, the selectivity of the column is high, and the separation effect is good.

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 element Pd 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 been proposed and some extracti...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B01D15/00B01J20/285G21F9/12
Inventor 张安运
Owner ZHEJIANG UNIV
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