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Method for adsorption separation of radioactive strontium-containing wastewater by hybrid membranes

An adsorption separation, hybrid membrane technology, applied in radioactive purification, nuclear engineering and other directions, can solve the problems of excessive use of chemical deposition reagents, difficult to meet actual needs, incomplete strontium ion treatment, etc., to achieve convenient cleaning and regeneration, increase resistance. Radiation performance, the effect of increasing the removal effect

Active Publication Date: 2018-11-02
HEFEI UNIV
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  • Claims
  • Application Information

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Problems solved by technology

[0003] Chinese patent application 201410009260.5 proposes a treatment method and device for radioactive strontium-containing wastewater, using strontium ions in radioactive wastewater to chemically react with calcium carbonate and sodium carbonate, so that strontium carbonate is deposited on the surface of calcium carbonate seed crystals to form large particles The dense crystal particles quickly settle to the bottom of the hydrocyclone to remove part of the radioactive strontium ions; the small particles of strontium carbonate and crystal seeds enter the membrane separator with the supernatant and react with ferric chloride, and the particles are separated by the hollow fiber membrane After further removing radioactive strontium ions, the radioactivity of the effluent is greatly reduced; this method mainly uses chemical substances to precipitate strontium ions, which has many processing steps, complicated operation process, more chemical deposition reagents, and incomplete treatment of strontium ions. Membrane fouling and other shortcomings, its application value is limited, it is difficult to meet the actual needs of large-scale industrial radioactive wastewater treatment
[0004] Chinese patent application 201610415050.5 proposes a treatment method for radioactive strontium-containing wastewater, which uses adding sodium carbonate into the reactor to make the strontium ions in the radioactive wastewater and sodium carbonate form large-grained precipitates, and then the radioactive wastewater enters the membrane separator, Finally, the radioactive wastewater is separated by reverse osmosis with a graphene oxide-based composite membrane; this method has many disadvantages, such as many processing steps, a large amount of precipitating agent, complicated operation process, and serious membrane pollution caused by membrane pore clogging, so its application value is limited.

Method used

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  • Method for adsorption separation of radioactive strontium-containing wastewater by hybrid membranes
  • Method for adsorption separation of radioactive strontium-containing wastewater by hybrid membranes
  • Method for adsorption separation of radioactive strontium-containing wastewater by hybrid membranes

Examples

Experimental program
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Effect test

Embodiment 1

[0041] A method for adsorbing and separating radioactive strontium-containing wastewater with a hybrid membrane, the specific steps are as follows:

[0042] (1) the preparation of the PVA aqueous solution that mass percent concentration is 5%

[0043]Add 50g of polyvinyl alcohol (PVA) with an average degree of polymerization of 1750±50 to a 500mL container equipped with a stirrer, then add an appropriate amount of deionized water, and in the air at a temperature of 93°C, continuously stir the PVA in the container. The mixture of PVA and water until the PVA is completely dissolved, continue to stir for 4 hours to obtain a solution, after cooling, transfer the solution to a 1000mL volumetric flask, add a certain amount of deionized water, shake evenly, and then add an appropriate amount of deionized water until the solution reaches Up to the full scale of the volumetric flask, shake it evenly again to prepare 1000g of PVA aqueous solution with a concentration of 5% by mass.

[...

Embodiment 2

[0058] Using the same experimental device, operating steps and the same ingredient ratio as in Example 1, the glass fiber cloth is immersed in the above-mentioned coating solution after static defoaming, and the coating film is dipped on the support glass fiber cloth until a membrane is obtained. , the membrane and glass fiber cloth were placed together at room temperature for 24 hours, and then they were convectively dried in a blast drying oven at 70°C for 4 hours. After cooling, the membrane and glass fiber cloth were not separated and the tape was obtained. Hybrid membrane with support glass fiber cloth.

[0059] The hybrid membrane prepared in this example was subjected to adsorption of 0.4g / L of SrCl 2 The experiment of strontium ions in the solution shows that: under the conditions of 25°C and pH=4, the hybrid film has no effect on Sr 2+ The adsorption rate is 90.6%. It can be seen that the hybrid film can be used to adsorb strontium ions in the strontium-containing aq...

Embodiment 3

[0062] Using the same experimental device, operating steps and the same ingredient ratio as in Example 1, first dissolve the coating solution with 20 mL of N,N-dimethylformamide (DMF), and then polymerize the obtained substance on the support Salivate coating on a tetrafluoroethylene plate (Teflon plate) until the diaphragm is obtained, let it stand at room temperature for 24 hours, then separate the diaphragm from the Teflon plate, dry the obtained diaphragm at 70°C for 2 hours, take it out and cool it to room temperature naturally That is, a hybrid membrane without a support is obtained.

[0063] The hybrid membrane prepared in this example was subjected to adsorption of 0.5g / L of SrCl 2 The experiment of strontium ions in the solution shows that: under the conditions of 30°C and pH=6, the hybrid film has no effect on Sr 2+ The adsorption rate is 87.5%. It can be seen that the hybrid film can be used to adsorb strontium ions in the strontium-containing aqueous solution.

...

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Abstract

The invention discloses a method for adsorption separation of radioactive strontium-containing wastewater by hybrid membranes. The method includes: firstly, feeding radioactive strontium-containing wastewater into a spiral-wound membrane separator, and adopting the hybrid membranes for adsorption separation of most of strontium ions in radioactive wastewater by cross-flow operation; secondly, feeding into a plate-type membrane separator, and adopting the hybrid membranes for adsorption removal of a small quantity of strontium ions in the wastewater by cross-flow operation; finally, performingreverse osmosis filtration treatment to remove residual trace strontium ions in the wastewater, so that the strontium ions in the radioactive strontium-containing wastewater are removed. The method for adsorption separation integrally has advantages of short process, simplicity and convenience in operation, easiness in cleaning and regeneration of the hybrid membranes, mild conditions, high selectivity, easiness in popularization and application and the like, large-scale removal of the strontium ions in the strontium-containing wastewater in the nuclear power industry can be realized, and themethod can also be used for adsorption removal of the strontium ions in non-radioactive wastewater.

Description

technical field [0001] The invention belongs to the technical field of radioactive wastewater treatment, and in particular relates to a method for absorbing and separating radioactive strontium-containing wastewater by a hybrid membrane. Background technique [0002] my country's "Nuclear Power Plant Medium and Long-term Development Plan" proposes that by 2020, the installed capacity of nuclear power plants will reach 40 million kilowatts, the proportion of nuclear power in the total installed capacity of electricity will increase from less than 2% at present to 4%, and the annual nuclear power generation will reach 2600-2800 100 million kWh; a number of nuclear power plants are currently under construction or demonstration. However, with the rapid development of nuclear power technology, nuclear power safety has attracted more attention. In particular, the Fukushima nuclear accident in Japan has sounded the alarm for us. How to effectively deal with low-concentration radioa...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/12
CPCG21F9/12
Inventor 刘俊生闫凯旋郑强松王敏胡恩柱
Owner HEFEI UNIV
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