CN106971767A - A kind of HTGR fuel element produces the processing method and processing device of waste water - Google Patents
A kind of HTGR fuel element produces the processing method and processing device of waste water Download PDFInfo
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- CN106971767A CN106971767A CN201710270427.7A CN201710270427A CN106971767A CN 106971767 A CN106971767 A CN 106971767A CN 201710270427 A CN201710270427 A CN 201710270427A CN 106971767 A CN106971767 A CN 106971767A
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- 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
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- 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
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- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
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Abstract
The invention provides the processing method that a kind of HTGR fuel element produces waste water, comprise the following steps：The pH value that HTGR fuel element is produced into waste water is adjusted to 6~6.8, filtered after neutralization precipitation, is obtained the first filtrate and filter cake, filtration cakes torrefaction is reclaimed；The mass content of ammonia is less than or equal to 2% in the HTGR fuel element production waste water；Complex-precipitation is carried out after first filtrate is mixed with alkaline calcium compound, phosphate, the second filtrate is filtrated to get；Second filtrate is subjected to charcoal absorption.The method that the present invention is provided can be effectively treated to uranium content for 1~1000ppm waste liquid, wherein more than 93.5% uranium can be recovered, the uranium content after processing in water outlet is less than 0.05ppm, and COD value is reduced to 100mg/L or so；And the secondary waste yield of method that the present invention is provided is few, a small amount of waste residue only is produced in complex-precipitation step, is adapted to scale processing.
Description
Technical field
Waste water is produced the present invention relates to Spent Radioactive water treatment field, more particularly to a kind of HTGR fuel element
Processing method and processing device.
Background technology
HTGR uses spheric fuel element, and the spheric fuel element has high chemical stability, thermally-stabilised
Property and mechanical stability, can be by the abundant detention of fuel fission product in reactor operation inside coated particle, effectively
Ground prevents leaking for radioactive dust and gas.Therefore, HTGR is one of current safest nuclear reaction heap-type.Element
Core is ceramic silica uranium particle, mainly prepares uranium dioxide core using outer gel method at present, and its key step includes molten
Solution, glue, scattered gelling, ageing, washing, drying and roasting, reduction, sintering, screening and sort etc., wherein dissolving, glue, disperseing
The wet method process section such as gelling, ageing, washing can produce a large amount of radioactive wastewaters containing materials such as ammonia, uranium, organic matter, nitrate.
HTGR fuel element production waste water ammonia content, content of organics, uranium content and salt (ammonium nitrate etc.) contain
Amount is all higher, larger with conventional uranium waste water difference.For this special water, Tsing-Hua University's power English etc. has invented a kind of NH3-N
A kind of recovery method (NH in Quan Ying, Chen Xiaotong, Wang Yang, Liu Bing, Tang Yaping, waste liquid containing ammonia3- N recovery method,
CN201310144190.X), the method is distilled using intermittent warming treatment, fed-batch pattern, and by cyclic absorption by waste liquid
In most of NH3- N is removed and recycled, while the effusion of radioactive element uranium is also avoid, the removal of final ammonia
Rate is more than 90%, and the concentration of ammonia is less than 1% in liquid after processing.
For this radioactive liquid waste removed after ammonia, it is (old that the red grades of Tsing-Hua University Chen Xiao have invented a kind of method of wastewater treatment
Dawn red, He Linfeng, Lu Zhenming, Liu Bing, Tang Yaping, the processing method of HTGR element core preparation technology waste water,
CN201410546584.2), the method uses flocculation sediment, charcoal absorption organics removal, silica gel absorption uranium, reverse osmosis concentration
Etc. process, it can make that uranium content is down to below 0.05ppm in water outlet after processing.Although the method can effectively remove the uranium in waste liquid
Element, but its method for using alum or alum/polyacrylamide to make flocculant is only suitable for handling the uranium-bearing waste liquid of low concentration
(below 10ppm), for the higher waste liquid of uranium content, flocculating effect is not good, and the secondary concentrated water and silicon of reverse osmosis process generation
The secondary solid waste such as glue is more.
The content of the invention
In view of this, it is an object of the invention to provide a kind of HTGR fuel element production that can be to high uranium content
The method that waste water is effectively treated, this method can efficiently be reclaimed to the uranium in waste liquid, effectively the COD of reduction waste water
Value, and handling process is short, secondary waste yield is few.
In order to realize foregoing invention purpose, the present invention provides following technical scheme：
A kind of HTGR fuel element produces the processing method of waste water, comprises the following steps：
The pH value that HTGR fuel element is produced into waste water is adjusted to 6~6.8, filtered after neutralization precipitation, is obtained
To the first filtrate and filter cake, filtration cakes torrefaction is reclaimed；The mass content of ammonia in the HTGR fuel element production waste water
Less than or equal to 2%；
Complex-precipitation is carried out after first filtrate is mixed with alkaline calcium compound, phosphate, the second filter is filtrated to get
Liquid；
Second filtrate is subjected to charcoal absorption.
It is preferred that, the temperature of the neutralization precipitation is 60~100 DEG C；The time of the neutralization precipitation is 30~120min.
It is preferred that, the temperature of the complex-precipitation is 60~100 DEG C；The time of the complex-precipitation is 30~120min.
It is preferred that, the alkaline calcium compound is calcium oxide and/or calcium hydroxide.
It is preferred that, the volume ratio of the quality of the alkaline calcium compound and the first filtrate is 0.2~5g：1L.
It is preferred that, the volume ratio of the phosphatic quality and the first filtrate is 0.2~10g：1L.
It is preferred that, the phosphate is sodium phosphate, potassium phosphate, ammonium phosphate, dibastic sodium phosphate, potassium hydrogen phosphate, ammonium hydrogen phosphate, phosphorus
One or more of mixtures in acid dihydride sodium, potassium dihydrogen phosphate and ammonium dihydrogen phosphate.
It is preferred that, the charcoal absorption uses activated-charcoal column.
The invention provides a kind of HTGR fuel element production wastewater treatment device, including waste liquid tank, neutralization
Precipitation reaction kettle, the first plate and frame filter press, complex-precipitation reaction kettle, the second plate and frame filter press and activated-charcoal column；The waste liquid tank
Delivery port be connected with the water inlet of neutralization-precipitation reaction kettle, the delivery port and the first plate compression of the neutralization-precipitation reaction kettle
The water inlet of machine is connected, and the delivery port of first plate and frame filter press is connected with the water inlet of complex-precipitation reaction kettle, the network
Close precipitation reaction kettle delivery port and the second plate and frame filter press water inlet be connected, the delivery port of second plate and frame filter press and
Activated-charcoal column water inlet is connected.
The invention provides the processing method that a kind of HTGR fuel element produces waste water, pass through neutralization precipitation, network
Close precipitation and charcoal absorption to handle HTGR fuel element production waste water, by neutralization precipitation by portion big absolutely in waste water
Divide uranium to reclaim, removed remaining uranium in waste liquid by complex-precipitation and charcoal absorption, and pass through steps of activated carbon adsorption
The COD value of waste water is greatly reduced.Embodiment shows that the method that the present invention is provided can be that 1~1000mg/L gives up to uranium content
Water is effectively treated, and more than 93.5% uranium can be recovered, and the uranium content after processing in water outlet is less than 0.05ppm, COD value
For 100mg/L or so；And secondary waste yield of the invention is few, a small amount of waste residue only is produced in complex-precipitation step, is adapted to scale
Change is handled.
Brief description of the drawings
Fig. 1 is the schematic diagram of HTGR fuel element production wastewater treatment device of the present invention；
In Fig. 1：1- waste liquid tanks；2- neutralization-precipitation reaction kettles；The plate and frame filter press of 3- first；4- complex-precipitation reaction kettles；5-
Second plate and frame filter press；6- activated-charcoal columns；7- pumps.
Embodiment
The invention provides the processing method that a kind of HTGR fuel element produces waste water, comprise the following steps：
The pH that HTGR fuel element is produced into waste water is adjusted to 6~6.8, filtered after neutralization precipitation, is obtained
First filtrate and filter cake, filtration cakes torrefaction is reclaimed；The mass content of ammonia is small in the HTGR fuel element production waste water
In equal to 2%；
Complex-precipitation is carried out after first filtrate is mixed with alkaline calcium compound, phosphate, the second filter is filtrated to get
Liquid；
Second filtrate is subjected to charcoal absorption.
The present invention adjusts the pH value that HTGR fuel element produces waste water to 6~6.8, carries out mistake after neutralization precipitation
Filter, obtains the first filtrate and filter cake, filtration cakes torrefaction is reclaimed；The quality of ammonia in the HTGR fuel element production waste water
Content is less than or equal to 2%.In the present invention, the mass content of ammonia is less than etc. in HTGR fuel element production waste water
In 2%, preferably less than equal to 1.5%.
In original HTGR fuel element production waste water the mass content of ammonia is about 17~25%, and a large amount of ammonia are deposited
It can cause to neutralize the substantial amounts of acid of needs, both add consumption of raw materials, a large amount of ammonium salts, the follow-up place of influence can be produced in the solution again
Manage effect.Therefore, the process object of the method for the invention is except the HTGR fuel element after ammonia produces waste water, this hair
Ammonia in waste water is evaporated off the bright ammonia still process method that preferably uses；The present invention does not have particular/special requirement to the detailed process of ammonia still process method, uses this
The conventional ammonia still process method in field.
Convenient for statement, the HTGR fuel element production waste water after this ammonia still process is handled in the present invention is referred to as
HTGR fuel element produces waste water；In the present invention, the HTGR fuel element produces the COD value of waste water about
For 2000~10000mg/L, uranium content is about 1~1000ppm.
The present invention adjusts the pH value that HTGR fuel element produces waste water to 6~6.8, preferably 6.2~6.5,
More preferably 6.3~6.4.PH value is adjusted present invention preferably uses acid solution；The acid solution is the mixture of concentrated acid and water；Institute
It is preferably the one or more in sulfuric acid, hydrochloric acid and nitric acid, more preferably sulfuric acid to state concentrated acid；Concentrated acid and water in the acid solution
Volume ratio is preferably 1:0~5, more preferably 1:2~4, most preferably 1:3.
In the present invention, the temperature of the neutralization precipitation is preferably 60~100 DEG C, more preferably 70~90 DEG C, most preferably
For 80~85 DEG C；The time of the neutralization precipitation is preferably 30~120min, more preferably 50~100min, most preferably 60~
80min；The present invention preferably carries out neutralization precipitation under agitation；The speed of the stirring is preferably 150~300 turns/min,
More preferably 200~250 turns/min.
After the neutralization precipitation, neutralization precipitation feed liquid is preferably naturally cooled to after room temperature and filtered by the present invention, obtains filter cake
With the first filtrate.The present invention does not have particular/special requirement to the specific method of filtering, and filter method well known to those skilled in the art is equal
Can, preferably suction filtration or plate compression, more preferably plate compression.
Obtain after filter cake, the present invention preferably reclaims filtration cakes torrefaction, and the temperature of the drying is preferably 80~200 DEG C, more
Preferably 100~180 DEG C, most preferably 120~150 DEG C.
In the present invention, in waste liquid more than 93.5% uranium by neutralization precipitation enter filter cake in, the filter cake it is main into
It is divided into ammonium diuranate, wherein uranium content is more than 63%, and the filter cake after recovery can directly be used as through high-temperature roasting prepares high temperature
The raw material of HTGR fuel element.
The present invention can be removed in waste water more than 93.5% uranium by neutralization precipitation, after neutralization precipitation is handled
To the first filtrate in uranium content be less than 15ppm, COD value slightly has reduction.
In alkalescent waste liquid containing ammonia, uranium is predominantly in the form of the larger ammonium uranyl tricarbonate of solubility, the present invention
System is neutralized to by subacidity by acid adding, ammonium uranyl tricarbonate is transformed into the smaller ammonium diuranate of solubility, so as to generate
Precipitation, while releasing carbon dioxide, promotes carbon dioxide to discharge by heating, so as to further promote chemical reaction equilibrium to the right
It is mobile, make uranium precipitation more thoroughly, be recycled, specifically chemically reacted such as the institute of formula 1 in filter cake so that most uranium enters
Show：
Obtain after the first filtrate, it is heavy that the present invention carries out complexing after the first filtrate is mixed with alkaline calcium compound, phosphate
Form sediment, be filtrated to get the second filtrate.In the present invention, the alkaline calcium compound is preferably calcium oxide and/or calcium hydroxide；It is described
Phosphate preferably includes sodium phosphate, potassium phosphate, ammonium phosphate, dibastic sodium phosphate, potassium hydrogen phosphate, ammonium hydrogen phosphate, sodium dihydrogen phosphate, phosphoric acid
One or more in potassium dihydrogen and ammonium dihydrogen phosphate, more preferably sodium dihydrogen phosphate；The quality of the alkaline calcium compound and
The volume ratio of first filtrate is preferably 0.2~5g：1L, more preferably 0.3~2g：1L, most preferably 0.5~1g：1L；The phosphorus
The quality of hydrochlorate and the volume ratio of the first filtrate are preferably 0.2~10g：1L, more preferably 1~4g：1L.
In the present invention, the temperature of the complex-precipitation is preferably 60~100 DEG C, more preferably 70~90 DEG C, most preferably
For 75~85 DEG C；The time of the complex-precipitation is preferably 30~120min, more preferably 50~100min, most preferably 70~
90min；The present invention preferably carries out complex-precipitation under agitation；The speed of the stirring is preferably 150~300 turns/min,
More preferably 200~250 turns/min.
The present invention ultimately forms hydroxyl using the uranium complexing in phosphate radical and the first filtrate with reference to alkaline calcium compound
Apatite Ca5(PO4)3(OH) part uranyl ion, is fixed on hydroxyapatite Ca5(PO4)3(OH) in lattice, simultaneously will
Part uranyl ion and the very tiny ammonium diuranate of residual precipitate granular absorption in the surface of hydroxyapatite and structure hole
In road, so as to reach the purpose for further removing uranium.
After the complex-precipitation, complex-precipitation feed liquid is preferably naturally cooled to after room temperature and filtered by the present invention, obtains second
Filtrate and filter residue.In the present invention, the method for the filtering is consistent with the filter method after neutralization precipitation, will not be repeated here；
Obtained filter residue can carry out curing process with cement, be transported to the repository storage of radiation solid waste.
The present invention can remove second obtained after in the first filtrate more than 90% uranium, complex-precipitation by complex-precipitation
Uranium content in filtrate is less than 2ppm, and COD value is slightly reduced in complex-precipitation step.
Obtain after the second filtrate, the second filtrate is preferably carried out charcoal absorption by the present invention.In the present invention, the activity
Charcoal absorption preferably uses activated-charcoal column；In a particular embodiment of the present invention, the second filtrate can be made to flow through activity from bottom to top
Charcoal post, to ensure optimal adsorption effect；Flow velocity of second filtrate in charcoal absorption is preferably 0.5~5L/min,
More preferably 1~4L/min, most preferably 2~3L/min.In the present invention, the specification of the activated-charcoal column is preferably Φ 10mm
× 50mm~Φ 15mm × 60mm, more preferably Φ 12mm × 55mm~Φ 14mm × 58mm；The activated-charcoal column is to organic matter
Adsorbance be preferably 40~100mg/g, more preferably 50~80mg/g, most preferably 60~70mg/g；The activated-charcoal column
Adsorbance to uranium is preferably 20~60mg/g, more preferably 30~50mg/g, most preferably 40~45mg/g；Charcoal absorption
It can be washed after saturation with dust technology, regeneration after drying.
HTGR fuel element production waste water in, the organic matter containing glue, such as tetrahydrofurfuryl alcohol, polyvinyl alcohol,
Ammonium of six methine four etc., has a small amount of uranium and these organic matters formation complex compound, is very by neutralization precipitation, phosphate complex-precipitation
It is difficult to remove this part uranium；The present invention utilizes the huge surface area and abundant pore structure of activated carbon, and its smaller to polarity
The stronger characteristic of organic matter adsorption capacity, the uranium of the organic matter in waste water and complex state is removed, further in reduction waste water
Uranium content.
In the present invention, the uranium content in charcoal absorption water outlet is less than 0.05ppm, and content of organics is in charcoal absorption
It is greatly lowered in step, the COD value of water outlet is only 100mg/L or so.
In the present invention, when the HTGR fuel element production Uranium in Waste Water content is more than or equal to 20ppm, pass through
Neutralization precipitation, complex-precipitation and the step of charcoal absorption three are reclaimed and removed to uranium, and the COD value of waste water is significantly dropped
It is low；When the HTGR fuel element production Uranium in Waste Water content is less than 20ppm, because uranium content is relatively low, in can omitting
The step of with precipitation, the removal of uranium is directly carried out by complex-precipitation and the step of charcoal absorption two；In the specific implementation of the present invention
In example, suitable processing procedure can be selected according to the composition of waste liquid.
The processing method of HTGR fuel element that the present invention is provided production waste water to the uranium in waste water and can have
Machine thing is effectively removed, and the uranium content and COD value in water outlet are all up state specified standards, and one is also contained in water outlet
Quantitative salt (about 10~40g/L), will carry out natural evaporation concentration, without carrying out other any places again after effluent collection
Reason.
The invention provides a kind of HTGR fuel element production wastewater treatment device, including waste liquid tank, neutralization
Precipitation reaction kettle, the first plate and frame filter press, complex-precipitation reaction kettle, the second plate and frame filter press and activated-charcoal column；The waste liquid tank
Delivery port be connected with the water inlet of neutralization-precipitation reaction kettle, the delivery port and the first plate compression of the neutralization-precipitation reaction kettle
The water inlet of machine is connected, and the delivery port of first plate and frame filter press is connected with the water inlet of complex-precipitation reaction kettle, the network
Close precipitation reaction kettle delivery port and the second plate and frame filter press water inlet be connected, the delivery port of second plate and frame filter press and
Activated-charcoal column water inlet is connected.
In the present invention, waste water is pumped into neutralization-precipitation reaction kettle 2 from after the outflow of the delivery port of waste liquid tank 1 and carries out neutralization precipitation,
The water outlet of neutralization-precipitation reaction kettle 2 enters the first plate and frame filter press 3 and carries out plate compression, and the first plate and frame filter press water outlet is pumped into network
Close precipitation reaction kettle 4 and carry out complex-precipitation, the water outlet of complex-precipitation reaction kettle enters the second plate and frame filter press 5 and carries out plate compression,
Second plate and frame filter press water outlet is pumped into activated-charcoal column 6 and carries out charcoal absorption, activated-charcoal column Chinese effluent to fuel from bottom to top
Element prepares in the special Natural Evaporating Ponds To The Atmosphere of factory and is evaporated concentration.
In the present invention, the neutralization precipitation, three step continuously-runnings of complex-precipitation and charcoal absorption, also can be only
Vertical operation, in a particular embodiment of the present invention, can select the suitable method of operation according to waste liquid composition.
The processing method for producing waste water to the HTGR fuel element that the present invention is provided with reference to embodiment is carried out
Detailed description, but they can not be interpreted as limiting the scope of the present invention.
Embodiment 1
100L waste water (pH=10.2, uranium content 508.00ppm) is pumped into neutralization-precipitation reaction kettle, in stirring condition
Under, plus sulfuric acid regulation system pH value is to 6.3, and system temperature then is heated into 85 DEG C, is incubated 60min, it is natural after reaction terminates
Room temperature is cooled to, feed liquid is extracted out, plate compression obtains the first filtrate and filter cake；Uranium content in first filtrate is detected,
Uranium content can be obtained for 12.32ppm, uranium clearance is up to 97.6%；Filter cake is dried and reclaimed, filter cake quality is 68.3g, is measured wherein
Uranium content is 71.2%, and the uranium rate of recovery is up to 95.7%；
First filtrate is pumped into complex-precipitation reaction kettle, 50g quick limes are added under agitation, are then added
200g sodium dihydrogen phosphates, 80 DEG C are heated to by system, are incubated 70min, after reaction terminates, are naturally cooled to room temperature, feed liquid is taken out
Go out, plate compression, obtain the second filtrate, it is 0.51ppm (510ppb) to measure uranium content in the second filtrate, and uranium clearance reaches
95.9%；Filter residue is temporary as secondary solid waste；
Second filtrate is pumped into activated-charcoal column from lower end, from the water outlet of activated-charcoal column upper end, Water discharge flow speed about 1L/min is controlled,
Uranium content and COD value detection are carried out to the water outlet of activated-charcoal column upper end, it is 0.04ppm that can obtain uranium content average value in water outlet
(40ppb), COD value is reduced to 118mg/L from the 7520mg/L of initial waste liquid.
Uranium and COD content balances are shown in Table 1 in each section of feed liquid before and after the processing and in processing procedure.
Table 1 uranium and COD contents in each section of feed liquid before and after the processing and in processing procedure
| Project | Waste water | First filtrate | Second filtrate | Water outlet |
| Uranium content (ppm) | 508.00 | 12.32 | 0.51 | 0.04 |
| COD value (mg/L) | 7520 | 7006 | 6752 | 118 |
Embodiment 2
100L waste liquids (pH=9.5, uranium content 126.00ppm) are pumped into neutralization-precipitation reaction kettle, under agitation
Plus then system temperature is heated to 85 DEG C by nitric acid regulation system pH value to 6.5,120min is incubated, it is naturally cold after reaction terminates
But to room temperature, feed liquid is extracted out, plate compression, obtains the first filtrate, it is 7.28ppm to measure uranium content in the first filtrate, uranium is removed
Rate is up to 94.2%；Filter cake is dried and reclaimed, filter cake quality is 18.5g, it is 63.7% to measure uranium content in filter cake, and the uranium rate of recovery reaches
93.5%；
First filtrate is pumped into complex reaction kettle, 30g milk of limes are added under agitation, 100g phosphorus is then added
Sour hydrogen ammonium, 80 DEG C are heated to by system, are incubated 120min, after reaction terminates, are naturally cooled to room temperature, feed liquid is extracted out, sheet frame
Press filtration, obtains the second filtrate, and it is 0.08ppm (80ppb) to measure in the second filtrate uranium content, and uranium clearance is up to 98.9%；Filter residue is made
It is temporary for secondary solid waste；
Second filtrate is pumped into activated-charcoal column from lower end, from the water outlet of activated-charcoal column upper end, Water discharge flow speed about 1L/min is controlled,
Uranium content and COD value detection are carried out to the water outlet of activated-charcoal column upper end, it is 0.03ppm that can obtain the uranium content average value in water outlet
(30ppb), COD value is reduced to 130mg/L from the 8135mg/L of initial waste liquid.
Uranium and COD content balances are shown in Table 2 in each section of feed liquid before and after the processing and in processing procedure.
Table 2 uranium and COD contents in each section of feed liquid before and after the processing and in processing procedure
| Project | Waste liquid | First filtrate | Second filtrate | Water outlet |
| Uranium content (ppm) | 126.00 | 7.28 | 0.08 | 0.03 |
| COD value (mg/L) | 8135 | 7763 | 6985 | 130 |
Embodiment 3
100L waste liquids (pH=9.8, uranium content is 2.67ppm) are pumped into complex-precipitation reaction kettle, under agitation,
30g milk of limes are added, 40g potassium hydrogen phosphates are then added, system is heated to 90 DEG C, 120min is incubated, it is natural after reaction terminates
Room temperature is cooled to, feed liquid is extracted out, plate compression obtains filtrate, it is 0.04ppm (40ppb), uranium clearance to measure wherein uranium content
Up to 98.5%；Filter residue is temporary as secondary solid waste；
Filtrate is pumped into activated-charcoal column from lower end, from the water outlet of activated-charcoal column upper end, Water discharge flow speed about 1L/min, water outlet is controlled
Uranium content average value be 0.02ppm (20ppb), COD value is reduced to 90mg/L from the 3250mg/L of initial waste liquid.
Uranium and COD content balances are shown in Table 3 in each section of feed liquid before and after the processing and in processing procedure.
Table 3 uranium and COD contents in each section of feed liquid before and after the processing and in processing procedure
| Project | Waste liquid | Filtrate | Water outlet |
| Uranium content (ppm) | 2.67 | 0.04 | 0.02 |
| COD value (mg/L) | 3250 | 2980 | 90 |
As seen from the above embodiment, the processing method for the HTGR fuel element production waste water that the present invention is provided can
Effective processing is carried out to the HTGR fuel element production waste water of high uranium content, wherein more than 93.5% uranium can be obtained
To recycling, the uranium content in water outlet is less than 0.05ppm, and COD value is reduced to 100 or so, and handling process is short, energy consumption compared with
Low, secondary waste yield is few, and operating cost is low, processing safety is high, can continuously run, and is adapted to scale processing.
Described above is only the preferred embodiment of the present invention, it is noted that for the ordinary skill people of the art
For member, under the premise without departing from the principles of the invention, some improvements and modifications can also be made, these improvements and modifications also should
It is considered as protection scope of the present invention.
Claims (9)
1. a kind of HTGR fuel element produces the processing method of waste water, it is characterised in that comprise the following steps：
The pH value that HTGR fuel element is produced into waste water is adjusted to 6~6.8, filtered after neutralization precipitation, obtains the
One filtrate and filter cake, filtration cakes torrefaction is reclaimed；The mass content of ammonia is less than in the HTGR fuel element production waste water
Equal to 2%；
Complex-precipitation is carried out after first filtrate is mixed with alkaline calcium compound, phosphate, the second filtrate is filtrated to get；
Second filtrate is subjected to charcoal absorption.
2. according to the method described in claim 1, it is characterised in that the temperature of the neutralization precipitation is 60~100 DEG C；In described
Time with precipitation is 30~120min.
3. according to the method described in claim 1, it is characterised in that the temperature of the complex-precipitation is 60~100 DEG C；The network
The time for closing precipitation is 30~120min.
4. according to the method described in claim 1, it is characterised in that the alkaline calcium compound is calcium oxide and/or hydroxide
Calcium.
5. method according to claim 4, it is characterised in that the body of the quality of the alkaline calcium compound and the first filtrate
Product is than being 0.2~5g：1L.
6. according to the method described in claim 1, it is characterised in that the phosphatic quality and the volume ratio of the first filtrate are
0.2~10g：1L.
7. the method according to claim 1 or 6, it is characterised in that the phosphate be sodium phosphate, potassium phosphate, ammonium phosphate,
One or more in dibastic sodium phosphate, potassium hydrogen phosphate, ammonium hydrogen phosphate, sodium dihydrogen phosphate, potassium dihydrogen phosphate and ammonium dihydrogen phosphate are mixed
Compound.
8. according to the method described in claim 1, it is characterised in that the charcoal absorption uses activated-charcoal column.
9. a kind of HTGR fuel element production wastewater treatment device, including waste liquid tank, neutralization-precipitation reaction kettle, first
Plate and frame filter press, complex-precipitation reaction kettle, the second plate and frame filter press and activated-charcoal column；The delivery port of the waste liquid tank and neutralization are heavy
The water inlet of shallow lake reactor is connected, and the delivery port of the neutralization-precipitation reaction kettle and the water inlet of the first plate and frame filter press are connected,
The delivery port of first plate and frame filter press is connected with the water inlet of complex-precipitation reaction kettle, and the complex-precipitation reaction kettle goes out
The mouth of a river is connected with the water inlet of the second plate and frame filter press, the delivery port and activated-charcoal column water inlet phase of second plate and frame filter press
Even.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710270427.7A CN106971767B (en) | 2017-04-24 | 2017-04-24 | A kind of processing method and processing device of high temperature gas cooled reactor fuel element production waste water |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710270427.7A CN106971767B (en) | 2017-04-24 | 2017-04-24 | A kind of processing method and processing device of high temperature gas cooled reactor fuel element production waste water |
Publications (2)
| Publication Number | Publication Date |
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| CN106971767A true CN106971767A (en) | 2017-07-21 |
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| CN108205009A (en) * | 2017-12-18 | 2018-06-26 | 中核北方核燃料元件有限公司 | The assay method of uranium content in a kind of spheric fuel element |
| CN109003693A (en) * | 2018-07-13 | 2018-12-14 | 清华大学 | A kind of spherical shape Nuclear Fuel Element Production Line method for treating waste liquid containing organic matter |
| CN112086216A (en) * | 2020-08-25 | 2020-12-15 | 广州大学 | Method for fixing uranyl ions in wastewater by using phosphate-enhanced nano zero-valent iron and application of method |
| CN114255899A (en) * | 2020-09-21 | 2022-03-29 | 西南科技大学 | Novel method for deeply purifying high-temperature gas cooled reactor core preparation process wastewater by utilizing enhanced flocculation sedimentation-advanced oxidation combined process |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108205009A (en) * | 2017-12-18 | 2018-06-26 | 中核北方核燃料元件有限公司 | The assay method of uranium content in a kind of spheric fuel element |
| CN109003693A (en) * | 2018-07-13 | 2018-12-14 | 清华大学 | A kind of spherical shape Nuclear Fuel Element Production Line method for treating waste liquid containing organic matter |
| CN109003693B (en) * | 2018-07-13 | 2019-10-25 | 清华大学 | A kind of spherical shape Nuclear Fuel Element Production Line method for treating waste liquid containing organic matter |
| CN112086216A (en) * | 2020-08-25 | 2020-12-15 | 广州大学 | Method for fixing uranyl ions in wastewater by using phosphate-enhanced nano zero-valent iron and application of method |
| CN112086216B (en) * | 2020-08-25 | 2022-11-01 | 广州大学 | Method for fixing uranyl ions in wastewater by using phosphate-enhanced nano zero-valent iron and application of method |
| CN114255899A (en) * | 2020-09-21 | 2022-03-29 | 西南科技大学 | Novel method for deeply purifying high-temperature gas cooled reactor core preparation process wastewater by utilizing enhanced flocculation sedimentation-advanced oxidation combined process |
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