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A material for treating typical radionuclides in wastewater and its application

A radionuclide and wastewater technology, applied in the field of environmental governance and environmental protection, can solve the problems of not meeting the requirements of radionuclide Sr adsorption treatment, less adsorption amount, less application of radionuclide, etc., achieving good application prospects and low cost , the effect of fast adsorption rate

Active Publication Date: 2018-02-16
INST OF HIGH ENERGY PHYSICS CHINESE ACAD OF SCI +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Traditional adsorption materials have a small amount of adsorption and cannot meet the current requirements for the adsorption of radionuclide Sr
[0004] Among the new adsorption materials, graphene (GO) materials and mesoporous molecular sieves (SBA-15) have been studied to have good adsorption effects, especially modified graphene materials (Hap-GO), while metal organic frameworks (MOFs ) materials are now mostly used in the adsorption treatment of heavy metals, and less used in the adsorption treatment of radionuclides. At present, there are only reports on the adsorption of radionuclide uranium (U)

Method used

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  • A material for treating typical radionuclides in wastewater and its application

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0024] Embodiment 1: Preparation of MOF material Ca-BTC

[0025] (1) 0.317g (1.8mmol) Ca(CH 3 COO) 2 ·H 2 O was dissolved in 60mL deionized water and stirred to obtain a homogeneous solution a;

[0026] (2) 0.378g (2mmol)H 3 BTC was dissolved in 18mL absolute ethanol and stirred to obtain a homogeneous solution b;

[0027] (3) Mix the two solutions of a and b at room temperature for 30 minutes to obtain a homogeneous solution, transfer it to a 100mL autoclave and heat it in an oven at 100°C for 24 hours, remove the reaction vessel, cool to room temperature, centrifuge, and use a large amount of ethanol Wash with deionized water;

[0028] (4) The obtained sample was placed in a vacuum drying oven at 100° C. for 10 h to obtain a Ca-BTC MOF material for use.

Embodiment 2

[0029] Example 2: Take the MOF material Ca-BTC prepared in Example 1 and adsorb Sr solution at 25°C

[0030] (1) Take 2000mg / LMOF material Ca-BTC, add 1000mg / L, pH=7 strontium nitrate solution, and place it in a water bath at 25°C;

[0031] (2) Take samples at 1 / 2 / 5 / 10 / 20 / 30 / 60 / 120 / 240 / 360 / 480 / 600 / 720min, dilute 10 4 times to be tested;

[0032] (3) ICP-OES measures the concentration of Sr and Ca in the solution, and calculates the adsorption amount by the formula;

[0033] (4) Make a graph of adsorption time and adsorption capacity, and the results are shown in Table 1.

Embodiment 3

[0034] Example 3: Take the MOF material Ca-BTC prepared in Example 1 and adsorb Sr solution at 35°C

[0035] (1) Take 2000mg / LMOF material Ca-BTC, add 1000mg / L, pH=7 strontium nitrate solution, and place it in a water bath at 35°C;

[0036] (2) Take samples at 1 / 2 / 5 / 10 / 20 / 30 / 60 / 120 / 240 / 360 / 480 / 600 / 720min, dilute 10 4 times to be tested;

[0037] (3) ICP-OES measures the concentration of Sr and Ca in the solution, and calculates the adsorption amount by the formula;

[0038] (4) Make a graph of adsorption time and adsorption capacity, and the results are shown in Table 1.

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Abstract

The invention provides a material for treating typical radionuclides in wastewater and application thereof and belongs to the technical field of environmental governance and environment protection. The benzoic acid MOF material of Ca is used for adsorbing the radionuclides in wastewater and is a trimesic acid MOF material of Ca or a terephthalic acid MOF material of Ca. By utilizing the characteristic that the capacity of bonding with trimesic acid or terephthalic acid of the radionuclides is higher than the capacity of bonding with trimesic acid or terephthalic acid of the Ca, the radionuclides are separated from the wastewater. The maximum adsorbing capacities of the novel material to the typical radionuclides such as strontium (Sr) are respectively up to 239.75 mg / g. The novel material has the good application prospect in treatment of typical radionuclides in domestic wastewater.

Description

technical field [0001] The invention relates to a Metal-Organic Framework (Metal-Organic Framework, MOF) material, its preparation and the material's adsorption treatment of strontium in simulated radioactive waste water. The invention is suitable for the treatment of radioactive waste water of typical radionuclides such as strontium (Sr) released during nuclear tests, nuclear accidents and nuclear energy reprocessing, and belongs to the technical field of environmental governance and environmental protection. Background technique [0002] Nuclear power energy has become a strategic choice for China's energy because of its economical, clean and efficient characteristics. However, the normal operation of nuclear power-related equipment produces a large amount of radioactive waste water, and the inevitable sudden nuclear accident leakage will bring extremely serious consequences. 90 Sr is 235 One of the main fission products of U, its half-life is about 28.9 years. It is on...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21F9/12C02F1/28
CPCC02F1/28G21F9/12
Inventor 马玲玲刘溪徐殿斗罗敏刘志明
Owner INST OF HIGH ENERGY PHYSICS CHINESE ACAD OF SCI