CN104795119A - Device, system and method for disposing radioactive waste water through forward osmosis - Google Patents
Device, system and method for disposing radioactive waste water through forward osmosis Download PDFInfo
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- CN104795119A CN104795119A CN201510223989.7A CN201510223989A CN104795119A CN 104795119 A CN104795119 A CN 104795119A CN 201510223989 A CN201510223989 A CN 201510223989A CN 104795119 A CN104795119 A CN 104795119A
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- Prior art keywords
- waste water
- radioactive
- wastewater
- forward osmosis
- chamber
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- 239000002354 radioactive wastewater Substances 0.000 title claims abstract description 67
- 238000000034 method Methods 0.000 title claims abstract description 29
- 238000009292 forward osmosis Methods 0.000 title claims abstract description 24
- 239000002351 wastewater Substances 0.000 claims abstract description 52
- 239000012528 membrane Substances 0.000 claims abstract description 46
- 239000007788 liquid Substances 0.000 claims abstract description 39
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 17
- 230000003204 osmotic effect Effects 0.000 claims abstract description 10
- -1 salt ions Chemical class 0.000 claims abstract description 6
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims description 24
- 230000002572 peristaltic effect Effects 0.000 claims description 12
- 239000011780 sodium chloride Substances 0.000 claims description 12
- 239000013535 sea water Substances 0.000 claims description 4
- 238000004065 wastewater treatment Methods 0.000 claims description 4
- 229910017052 cobalt Inorganic materials 0.000 abstract description 11
- 239000010941 cobalt Substances 0.000 abstract description 11
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 abstract description 11
- 238000001704 evaporation Methods 0.000 abstract description 8
- 238000005265 energy consumption Methods 0.000 abstract description 6
- 230000008020 evaporation Effects 0.000 abstract description 6
- 238000001223 reverse osmosis Methods 0.000 abstract description 6
- 238000005516 engineering process Methods 0.000 abstract description 4
- 230000007797 corrosion Effects 0.000 abstract description 3
- 238000005260 corrosion Methods 0.000 abstract description 3
- 238000004880 explosion Methods 0.000 abstract description 3
- 238000005187 foaming Methods 0.000 abstract description 3
- 230000005494 condensation Effects 0.000 abstract 1
- 238000009833 condensation Methods 0.000 abstract 1
- 239000000243 solution Substances 0.000 description 28
- 239000011550 stock solution Substances 0.000 description 5
- 229910001429 cobalt ion Inorganic materials 0.000 description 4
- XLJKHNWPARRRJB-UHFFFAOYSA-N cobalt(2+) Chemical compound [Co+2] XLJKHNWPARRRJB-UHFFFAOYSA-N 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 238000002474 experimental method Methods 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- 229920002284 Cellulose triacetate Polymers 0.000 description 2
- NNLVGZFZQQXQNW-ADJNRHBOSA-N [(2r,3r,4s,5r,6s)-4,5-diacetyloxy-3-[(2s,3r,4s,5r,6r)-3,4,5-triacetyloxy-6-(acetyloxymethyl)oxan-2-yl]oxy-6-[(2r,3r,4s,5r,6s)-4,5,6-triacetyloxy-2-(acetyloxymethyl)oxan-3-yl]oxyoxan-2-yl]methyl acetate Chemical compound O([C@@H]1O[C@@H]([C@H]([C@H](OC(C)=O)[C@H]1OC(C)=O)O[C@H]1[C@@H]([C@@H](OC(C)=O)[C@H](OC(C)=O)[C@@H](COC(C)=O)O1)OC(C)=O)COC(=O)C)[C@@H]1[C@@H](COC(C)=O)O[C@@H](OC(C)=O)[C@H](OC(C)=O)[C@H]1OC(C)=O NNLVGZFZQQXQNW-ADJNRHBOSA-N 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 239000012466 permeate Substances 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 229910021580 Cobalt(II) chloride Inorganic materials 0.000 description 1
- 239000004952 Polyamide Substances 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000004134 energy conservation Methods 0.000 description 1
- 230000010287 polarization Effects 0.000 description 1
- 229920002647 polyamide Polymers 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000012552 review Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
The invention discloses a device, system and method for disposing radioactive waste water through forward osmosis and aims at solving the problem that the prior art is high in energy consumption. The device comprises a semi-permeable membrane, a sucking chamber and a waste water chamber, wherein water molecules can pass through the semi-permeable membrane, salt ions cannot pass through the semi-permeable membrane, the sucking chamber is used for allowing sucked liquid to pass through, the waste water chamber is used for allowing the radioactive waste water to pass through, and the sucking chamber is partitioned from the waste water chamber through the semi-permeable membrane; the osmotic pressure of the sucked liquid is larger than that of the radioactive waste water. According to the device, system and method for disposing the radioactive waste water through the forward osmosis, the fact that osmotic pressures exist in the sucked liquid and the waste water at the two sides of the membrane is utilized, and water is permeated from the waste water side to the sucked liquid side through the permeable membrane, so that the condensation of the waste water containing cobalt is achieved. By means of the device, system and method for disposing the radioactive waste water through the forward osmosis, potential hazards in the traditional evaporation technology such as foaming, corrosion, scaling and explosion can be effectively overcome, meanwhile, compared with a reverse osmosis method, the method has the advantages of being low in energy consumption, little in membrane pollution, low in quality requirement for input water, long in membrane component replacement cycle and the like.
Description
Technical Field
The invention relates to a device, a system and a method for treating radioactive wastewater by forward osmosis.
Background
In recent years, China speeds up the construction pace of nuclear power industry, and the treatment of nuclear waste is more and more concerned by people while nuclear power is vigorously developed. Particularly, the recent Japanese Fudao nuclear leakage accident enables people all over the world to review the development of nuclear power. Whether radioactive wastewater discharged by a nuclear power station can be timely and effectively treated becomes an important restriction factor for nuclear power development.
Because the final solidification treatment of radioactive waste is very costly, the reduction treatment of waste water is the most critical step in the whole treatment process in radioactive waste water treatment. The nuclear power plant in developed countries mainly adopts evaporation and membrane treatment methods and the combination of these processes to achieve the purpose of reduction. The reduction treatment of radioactive wastewater is mainly carried out by adopting an evaporation method in China. The evaporation process is a traditional, reliable concentration process used by most nuclear power plants. The main disadvantages of the evaporation method are high energy consumption and high operation cost, and meanwhile, because small liquid drops generated in the evaporation process enter the condensate along with water vapor, the condensate needs to be further treated, the equipment is complex, and meanwhile, the design of the evaporation process also needs to consider potential risks such as foaming, corrosion, scaling, explosion and the like.
In the application of the membrane treatment technology in radioactive wastewater reduction, a reverse osmosis method is mainly used, and a part of foreign existing power plants adopt a reverse osmosis process to treat part of radioactive wastewater. Because the reverse osmosis technology has been industrially applied for many years, the technology is relatively mature, the separation effect on nuclides in radioactive wastewater is good, and the amount of generated secondary wastewater is small, so that more application attempts are made in recent years. However, the water inlet pressure is high, so that the energy consumption is high, the requirement on equipment is high, and the pollution condition of the concentration polarization membrane is serious.
In view of the defects of the existing process, the search for a novel efficient, energy-saving and safe concentration treatment process becomes an urgent problem to be solved in radioactive wastewater treatment.
Disclosure of Invention
In order to overcome the defects, the invention aims to provide a device, a system and a method for treating radioactive wastewater by forward osmosis, which have the advantages of simple direction, high efficiency, energy conservation and safety.
In order to achieve the above object, the present invention provides an apparatus for treating radioactive wastewater by forward osmosis, comprising:
water molecules can pass through the semi-permeable membrane which salt ions cannot pass through;
a draw chamber for passage of draw solution;
and a waste water chamber for passing radioactive waste water,
the drawing chamber and the waste water chamber are separated by the semi-permeable membrane; wherein,
the osmotic pressure of the drawing liquid is greater than that of the radioactive wastewater.
Wherein the drawing solution is high-concentration NaCl solution and seawater.
In order to achieve the above object, the present invention provides a system for treating radioactive wastewater by forward osmosis, comprising: the radioactive wastewater treatment apparatus as described above; further comprising:
a draw solution input conduit for providing draw solution to the draw chamber and an output conduit for receiving draw solution through the draw chamber;
a waste water input conduit for providing radioactive waste water to the waste water chamber and a waste water output conduit for receiving the radioactive waste water through the waste water chamber.
Preferably, a peristaltic pump, a flow meter and a conductivity meter are arranged on the pipeline.
Preferably, the device also comprises a waste water tank; the wastewater input pipeline and the wastewater output pipeline are communicated with the wastewater tank to form a circulation loop.
Preferably, the device also comprises a drawing liquid tank; the drawing liquid input pipeline and the drawing liquid output pipeline are communicated with the waste water tank to form a circulation loop. Or the circulating loop intermittently or continuously supplies NaCl to maintain the concentration of the drawing solution unchanged. Or an open continuous flow, such as a seawater supply.
Preferably, the flow rate of the draw solution and the waste water is not less than 1.85 cm/s.
Preferably, the concentration of the drawing solution is not lower than 0.5mol/L (calculated by NaCl); preferably, the concentration of the radioactive waste water is not higher than 20mg/L (calculated by Co).
In order to achieve the above object, the method for treating radioactive wastewater by forward osmosis of the present invention comprises the steps of:
selecting a semi-permeable membrane through which water molecules can pass but salt ions cannot pass;
one side of the semi-permeable membrane through which draw solution passes;
one side of a semi-permeable membrane for radioactive wastewater; wherein,
the osmotic pressure of the drawing liquid is greater than that of the radioactive wastewater.
Preferably, the draw solution works in a circulating mode, and the concentration of the draw solution is kept to be not lower than 0.5mol/L in the circulating process.
The invention has the beneficial effects that: according to the invention, the osmotic pressure between the drawing liquid on the two sides of the membrane and the wastewater is utilized, and water permeates from the wastewater side to the drawing liquid side through the osmotic membrane, so that the concentration of the cobalt-containing wastewater is realized. The invention can effectively overcome the potential risks of foaming, corrosion, scaling, explosion and the like in the traditional evaporation process, and simultaneously has the advantages of low energy consumption, small membrane pollution, low requirement on the quality of inlet water, long membrane component replacement period and the like compared with a reverse osmosis method.
Drawings
FIG. 1 is a schematic view of an apparatus for separating radioactive wastewater according to an embodiment 1 of the present invention.
In the figure, 1-a waste water chamber, 2-a peristaltic pump, 3-a flow meter, 4-a waste water tank, 5-a liquid drawing tank, 6-a conductivity meter and 7-a drawing chamber
Detailed description of the invention
The invention is further described with reference to the following figures and specific examples.
The apparatus for treating radioactive wastewater by forward osmosis of the present invention, as shown in fig. 1, comprises: water molecules can pass through the semi-permeable membrane which salt ions cannot pass through; a drawing chamber 7 for passing drawing liquid; and a waste water chamber 1 for the passage of radioactive waste water, said drawing chamber 1 and waste water chamber 7 being separated by said semi-permeable membrane; wherein the osmotic pressure of the drawing liquid is greater than that of the radioactive wastewater. Wherein the drawing solution is NaCl solution with the concentration not less than 0.5mol/L and seawater.
The side of the semipermeable membrane through which the draw solution passes in use; one side of a semi-permeable membrane for radioactive wastewater; because the osmotic pressure of the drawing liquid is larger than that of the radioactive wastewater. Water permeates from the wastewater side to the draw solution side through the permeable membrane, thereby effecting concentration of the radioactive wastewater. Compared with the reverse osmosis method, the method has the advantages of low energy consumption, small membrane pollution, low requirement on the quality of inlet water, long membrane component replacement period and the like.
Following by CoCl2·6H2And O is used as a material, and 1000mL of solution containing cobalt ions with a certain concentration is prepared and used as simulated radioactive wastewater.
Example 1
The device for separating cobalt in radioactive wastewater by forward osmosis in the embodiment is shown in fig. 1, and comprises a membrane contact chamber 1, a peristaltic pump 2, a flow meter 3, a wastewater tank 4, a drawing liquid tank 5, and a conductivity meter 6; one side of the membrane contact chamber 1 is communicated with a waste water tank 4 through a pipeline to form a circulating loop. The other side of the membrane component 1 is communicated with a liquid drawing tank 5 through a pipeline to form a circulation loop. The peristaltic pump 2 and the flow meter 3 are connected in two circulation loops formed on two sides of the membrane contact chamber 1.
The experiment for separating cobalt in radioactive wastewater by adopting the device is as follows: simulated radioactive wastewater with a cobalt ion concentration of 20mg/L and a volume of 1L is added into the wastewater tank. Adding 1mol/L sodium chloride solution into the drawing liquid tank, wherein the volume is 1L. Starting the respective peristaltic pumps of the stock solution circulating loop and the draw solution circulating loop to ensure that the flow rates of the two circulating loops are both 1.85cm/s and the temperatures of the circulating loops are both 18 ℃ (room temperature). Film material: a polyamide composite film. The film direction: the active layer faces the draw solution.
The results show that: the average water flux is 3.67L/(m)2H), the cobalt rejection was 97.0%.
Example 2
The device for separating cobalt in radioactive wastewater by forward osmosis in the embodiment is shown in fig. 1, and comprises a membrane contact chamber 1, a peristaltic pump 2, a flow meter 3, a wastewater tank 4, a drawing liquid tank 5, and a conductivity meter 6; one side of the membrane contact chamber 1 is communicated with a waste water tank 4 through a pipeline to form a circulating loop. The other side of the membrane component 1 is communicated with a liquid drawing tank 5 through a pipeline to form a circulation loop. The peristaltic pump 2 and the flow meter 3 are connected in two circulation loops formed on two sides of the membrane contact chamber 1.
The experiment for separating cobalt in radioactive wastewater by adopting the device is as follows: simulated radioactive wastewater with the cobalt ion concentration of 20mg/L is added into the wastewater tank, and the volume of the simulated radioactive wastewater in the wastewater circulation loop is 1L. Adding a sodium chloride solution with the concentration of 1mol/L into a drawing liquid tank, wherein the volume of the sodium chloride in a drawing liquid circulation loop is 1L. And starting respective peristaltic pumps of the draw solution circulation loop and the stock solution circulation loop to ensure that the flow rates of the simulated radioactive wastewater and the draw solution are both 11.1cm/s, and the temperatures of the draw solution circulation loop and the stock solution circulation loop are 24 ℃ (room temperature). In the test, NaCl is supplemented in the drawing liquid tank every 30 minutes, so that the concentration of the drawing liquid is always maintained at 1 mol/L. Film material: cellulose triacetate membranes. The film direction: the active layer faces the simulated radioactive wastewater.
The results show that: the average water flux is 15.07L/(m)2H), the cobalt rejection was 99.47%.
Example 3
The device for separating cobalt in radioactive wastewater by forward osmosis in the embodiment is shown in fig. 1, and comprises a membrane contact chamber 1, a peristaltic pump 2, a flow meter 3, a wastewater tank 4, a drawing liquid tank 5, and a conductivity meter 6; one side of the membrane contact chamber 1 is communicated with a waste water tank 4 through a pipeline to form a circulating loop. The other side of the membrane component 1 is communicated with a liquid drawing tank 5 through a pipeline to form a circulation loop. The peristaltic pump 2 and the flow meter 3 are connected in two circulation loops formed on two sides of the membrane contact chamber 1.
The experiment for separating cobalt in radioactive wastewater by adopting the device is as follows: simulated radioactive wastewater with the cobalt ion concentration of 20mg/L is added into the wastewater tank, and the volume of the simulated radioactive wastewater in the wastewater circulation loop is 1L. Adding a sodium chloride solution with the concentration of 0.5mol/L into a drawing liquid tank, wherein the volume of the sodium chloride in a drawing liquid circulation loop is 1L. And starting respective peristaltic pumps of the draw solution circulation loop and the stock solution circulation loop to ensure that the flow rates of the simulated radioactive wastewater and the draw solution are both 11.1cm/s, and the temperatures of the draw solution circulation loop and the stock solution circulation loop are 24 ℃ (room temperature). In the test, NaCl is supplemented to the drawing liquid tank every 10 minutes, so that the concentration of the drawing liquid is always maintained at 0.5 mol/L. Film material: cellulose triacetate membranes. The film direction: the active layer faces the simulated wastewater.
The results show that: the water flux is 8.28L/(m)2H), the cobalt rejection was 98.59%.
Claims (10)
1. The utility model provides a device of radioactive waste water is handled to forward osmosis which characterized in that: the method comprises the following steps:
water molecules can pass through the semi-permeable membrane which salt ions cannot pass through;
a draw chamber for passage of draw solution;
and a waste water chamber for passing radioactive waste water,
the drawing chamber and the waste water chamber are separated by the semi-permeable membrane; wherein,
the osmotic pressure of the drawing liquid is greater than that of the radioactive wastewater.
2. The apparatus for forward osmosis treatment of radioactive wastewater of claim 1, wherein: the drawing liquid is seawater or NaCl solution with the concentration of more than 0.5 mol/L.
3. A system for forward osmosis treatment of radioactive wastewater, comprising: the radioactive wastewater treatment apparatus according to claim 1; further comprising:
a draw solution input conduit for providing draw solution to the draw chamber and an output conduit for receiving draw solution through the draw chamber;
a waste water input conduit for providing radioactive waste water to the waste water chamber and a waste water output conduit for receiving the radioactive waste water through the waste water chamber.
4. A system for forward osmosis treatment of radioactive wastewater as claimed in claim 3, wherein: the pipeline is provided with a peristaltic pump, a flowmeter and a conductivity meter.
5. A system for forward osmosis treatment of radioactive wastewater as claimed in claim 3, wherein: also comprises a waste water tank; the wastewater input pipeline and the wastewater output pipeline are communicated with the wastewater tank to form a circulation loop.
6. A system for forward osmosis treatment of radioactive wastewater as claimed in claim 3, wherein: the device also comprises a liquid drawing tank; the drawing liquid input pipeline and the drawing liquid output pipeline are communicated with the waste water tank to form a circulation loop.
7. A system for forward osmosis treatment of radioactive wastewater as claimed in claim 3, wherein: the flow rate of the drawing liquid and the waste water is not lower than 1.85 cm/s.
8. A system for forward osmosis treatment of radioactive wastewater as claimed in claim 3, wherein: the concentration of the drawing liquid is not lower than 0.5 mol/L; the concentration of the radioactive wastewater is not higher than 20 mg/L.
9. A method for treating radioactive wastewater by forward osmosis is characterized by comprising the following steps:
selecting a semi-permeable membrane through which water molecules can pass but salt ions cannot pass;
one side of the semi-permeable membrane through which draw solution passes;
one side of a semi-permeable membrane for radioactive wastewater; wherein,
the osmotic pressure of the drawing liquid is greater than that of the radioactive wastewater.
10. The method for the forward osmosis treatment of radioactive wastewater as claimed in claim 9, wherein said draw solution is operated in a circulating manner, and a concentration of said draw solution is maintained at not less than 0.5mol/L during the circulation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510223989.7A CN104795119A (en) | 2015-05-05 | 2015-05-05 | Device, system and method for disposing radioactive waste water through forward osmosis |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201510223989.7A CN104795119A (en) | 2015-05-05 | 2015-05-05 | Device, system and method for disposing radioactive waste water through forward osmosis |
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| CN104795119A true CN104795119A (en) | 2015-07-22 |
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| CN201510223989.7A Pending CN104795119A (en) | 2015-05-05 | 2015-05-05 | Device, system and method for disposing radioactive waste water through forward osmosis |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108862490A (en) * | 2018-07-16 | 2018-11-23 | 山东大学 | A kind of device and method using nitrogen phosphorus in conductive positive osmosis process recycling waste water |
| CN109876663A (en) * | 2019-03-08 | 2019-06-14 | 天津工业大学 | A kind of algae solution dehydration device and method based on the positive infiltration technology of dead end |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108862490B (en) * | 2018-07-16 | 2021-09-17 | 山东大学 | Device and method for recycling nitrogen and phosphorus in wastewater by utilizing conductive forward osmosis process |
| CN109876663A (en) * | 2019-03-08 | 2019-06-14 | 天津工业大学 | A kind of algae solution dehydration device and method based on the positive infiltration technology of dead end |
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