Recovery method for trace of uranium and/or plutonium in radioactive organic liquid waste

An organic waste liquid, radioactive technology, applied in the direction of radioactive purification, nuclear engineering, etc., to achieve the effect of recycling and reducing the amount of waste

Inactive Publication Date: 2015-11-04
PEKING UNIV
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, CO in the stripped aqueous phase 3 2- The higher concentration of , competes with the ligand group for UO 2 2+ the situation is more serious

Method used

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  • Recovery method for trace of uranium and/or plutonium in radioactive organic liquid waste
  • Recovery method for trace of uranium and/or plutonium in radioactive organic liquid waste
  • Recovery method for trace of uranium and/or plutonium in radioactive organic liquid waste

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Embodiment 1

[0033] (1) Materials and methods

[0034] 1. Experimental materials

[0035] Uranyl nitrate (UO 2 (NO 3 ) 2 ·6H 2 O, G.R.), ammonium uranyl carbonate ((NH 4 ) 4 [UO 2 (CO 3 ) 3 ], prepared according to the literature: Wu Keming, Solubility of Ammonium Uranyl Carbonate [J]. Atomic Energy Science and Technology, 1961,3(3):148-156. Sodium carbonate (Na 2 CO 3 ), tributyl phosphate (TBP), dodecane, ferrous ammonium sulfate, and hydroxylamine hydrochloride are commercially available reagents of analytical grade and used directly. Acrylic acid (AA) and acrylonitrile (AN) were commercially available reagents of analytical grade and were purified by vacuum distillation before use. Acrylamide (AAm) is a commercially available reagent of analytical grade and was purified by recrystallization before use. Polypropylene (PP, 20 mesh) powder was provided by Beijing Research Institute of Chemical Industry. Before use, it was extracted with acetone in a Soxhlet extractor for 24 h...

Embodiment 2

[0078]According to the literature (H.J.Zhang, H.L.Liang, Q.D.Chen, X.H.Shen.Synthesis of a new ionic imprinted polymer for the extraction of uranium from seawater[J].J.Radioanal.Nucl.Chem.,2013,298:1705-1712. ) to synthesize (2,4-dicarbonyl)-3-pentyl methacrylate, and use it as a functional monomer, ethylene glycol dimethacrylate as a crosslinking agent, and 1,4-dioxane as a solvent Preparation of imprinted polymers targeting uranyl ions. The screened 100-200 mesh polymer particles are packed into a column with a diameter of 10 mm, and the polymer filling height is 100 mm. The concentration of uranium is 35mg·L -1 The aqueous ammonium uranyl carbonate solution was used for column chromatography, and the flow rate was controlled at 10mL min -1 , every outflow 10mL sampling monitoring U(VI) concentration. When the presence of U(VI) is detected in the effluent, the total volume of the previous effluent is the breakthrough volume of the chromatographic column. The breakthrough...

Embodiment 3

[0082] According to literature (S.Das, A.K.Pandey, A.A.Athawale, V.Natarajan, V.K.Manchanda.Uranium preconcentration from seawater using phosphate functionalized poly(propylene) fibrous membrane [J].Desalin.Water Treat.,2012,38:114-120 .), grafted 2-(phosphoryloxy)ethanol methacrylate (PP-g-PEGMP) on the porous polypropylene membrane by gamma-ray irradiation method, the grafting rate was 93.5%, and in the grafted product The density of phosphoryloxy is 2.3mmol·g -1 . Cut into a circular membrane with a diameter of 55mm, as a filter membrane, the concentration of uranium is 35mg L -1 The aqueous solution of ammonium uranyl carbonate was filtered under pressure (the effective diameter of the membrane was 50mm), and the flow rate was controlled at 5mL·min -1 , monitor the concentration of U(VI) by sampling every 5mL outflow. When the presence of U(VI) is detected in the effluent, the total volume of the previous effluent is the breakthrough volume of the chromatographic column...

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Abstract

The prevent invention discloses a method for recovering a trace of uranium and/or plutonium from radioactive organic liquid waste. The method comprises: firstly, performing stripping on radioactive organic liquid waste with a carbonate solution; then performing oscillation adsorption, column chromatography or membrane filtration on a stripped aqueous phase by using a solid functional adsorption material; recycling a treated liquid again as a stripping solution; using acid to perform elution on the solid functional adsorption material that adsorbs the uranium and/or plutonium, to obtain a rich aqueous solution containing the uranium and/or plutonium; recycling the adsorption material after the elution by using an aqueous bicarbonate solution for soaking or washing. The method combines stripping of carbonate and recycling of a low concentration of uranium and/or plutonium from a (weak) alkaline aqueous solution, and achieves recycling of the functional adsorption material and the stripping solution, thereby reducing the amount of waste as much as possible.

Description

technical field [0001] The invention relates to a treatment method for radioactive organic waste liquid, in particular to a method for efficiently enriching and recovering uranium and / or plutonium from radioactive organic waste liquid containing trace amounts of uranium and / or plutonium. Background technique [0002] Uranium and plutonium are important nuclear materials in the nuclear industry. During the use and research of uranium and plutonium, the separation and enrichment of uranium and plutonium is an important task. At present, liquid-liquid extraction based on tributyl phosphate (TBP) is still the most commonly used and mature separation technology for uranium and plutonium. However, in the process of liquid-liquid extraction and separation, a large amount of organic waste liquid containing uranium and plutonium will inevitably be produced. Among them, the content of uranium and plutonium is low, and the source and composition are relatively complicated, so there is...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/12
Inventor 沈兴海陈庆德郭倚天
Owner PEKING UNIV
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