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Method for separating heating element Cs and Sr from high 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 safe and effective treatment and disposal, good separation effect and easy adjustment

Inactive Publication Date: 2008-03-19
ZHEJIANG UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] However, after the nitric acid solution of high-level waste is separated from minor actinides, it also contains metal elements such as Cs, Sr, Rh, and Ru, and the exothermic elements Cs and Sr must also be separated. This patent does not involve Cs, Sr, Rh, Further separation of metal elements such as Ru

Method used

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  • Method for separating heating element Cs and Sr from high radioactive waste
  • Method for separating heating element Cs and Sr from high radioactive waste
  • Method for separating heating element Cs and Sr from high radioactive waste

Examples

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Embodiment 1

[0050] The preparation of embodiment 1 adsorbent A

[0051] Dissolve 100 g of Calix[4]arene-R14 (with structural formula (II)) and 60 g of tributylphosphate (TBP) in 500 mL of dichloromethane and mix well; add 200 g of polymer-coated 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

[0052] Example 2 Preparation of Adsorbent A

[0053] Dissolve 100 g of Calix[4]arene-R14 (with structural formula (II)) and 40 g of tributylphosphate (TBP) in 2000 mL of dichloromethane and mix well; add 1000 g of polymer-coated 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

[0054] Example 3 Preparation of Adsorbent A

[0055] Dissolve 100 g of Calix[4]arene-R14 (with structural formula (II)) and 100 g of tributyl phosphate (TBP) in 3000 mL of dichloromethane and mix well; add 1500 g of polymer-coated 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 of separating heating elements Cs and Sr from high level radioactive waste. The method contains the following steps: (1) concentrated nitric acid is added into the nitrate solution of high level radioactive waste that the secondary actinide is separated; the concentration of the nitric acid is adjusted to 3.5-4.4 mol / L; (2) the nitrate solution of high level radioactive waste that the nitric acid concentration is adjusted passes by a chromatographic column filled with adsorbent A, and the heating element Cs is absorbed by the chromatographic column filled with adsorbent A; (3) after the nitrate solution of high level radioactive waste that the nitric acid concentration is adjusted flowing out of the chromatographic column filled with adsorbent A, water is added and the concentration of the nitric acid is adjusted to 1.5-2.5 mol / L; and when the solution passes by the a chromatographic column filled with adsorbent B, the heating element Sr is absorbed by the chromatographic column filled with adsorbent B. The method is simple with high efficiency. The concentration of the nitric acid is similar when the two chromatographic column adsorptions are separated, which is convenient to be adjusted.

Description

technical field [0001] The invention relates to the field of reprocessing of high-level radioactive waste in nuclear industry, especially the separation of heating elements Cs and Sr in 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). and almost all FP elements went into HLLW. For long-lived MA, separation / transmutation technology has been proposed and some e...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): B01D15/08B01J20/26G21F9/12C22B26/00
Inventor 张安运
Owner ZHEJIANG UNIV
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