CN106971767B - A kind of processing method and processing device of high temperature gas cooled reactor fuel element production waste water - Google Patents
A kind of processing method and processing device of high temperature gas cooled reactor fuel element production waste water Download PDFInfo
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- CN106971767B CN106971767B CN201710270427.7A CN201710270427A CN106971767B CN 106971767 B CN106971767 B CN 106971767B CN 201710270427 A CN201710270427 A CN 201710270427A CN 106971767 B CN106971767 B CN 106971767B
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- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
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Abstract
The present invention provides a kind of processing methods of high temperature gas cooled reactor fuel element production waste water, the following steps are included: the pH value of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8, it is filtered after carrying out neutralization precipitation, obtains the first filtrate and filter cake, filtration cakes torrefaction is recycled；The mass content of ammonia is less than or equal to 2% in the high temperature gas cooled reactor fuel element production waste water；Complex-precipitation is carried out after first filtrate is mixed with alkaline calcium compound, phosphate, the second filtrate is obtained by filtration；Second filtrate is subjected to activated carbon adsorption.Method provided by the invention can be effectively treated the waste liquid that uranium content is 1~1000ppm, wherein 93.5% or more uranium can be recovered, the uranium content after processing in water outlet is lower than 0.05ppm, and COD value is reduced to 100mg/L or so；And the secondary waste yield of method provided by the invention is few, only generates a small amount of waste residue in complex-precipitation step, is suitble to scale processing.
Description
Technical field
The present invention relates to Spent Radioactive water treatment fields more particularly to a kind of high temperature gas cooled reactor fuel element to produce waste water
Processing method and processing device.
Background technique
High temperature gas cooled reactor uses spheric fuel element, which has high chemical stability, thermostabilization
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, high temperature gas cooled reactor 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, key step includes molten
Solution, glue, dispersion gelling, ageing, washing, drying and roasting, reduction, sintering, screening and sorting etc., wherein dissolution, glue, dispersion
The wet processes process sections such as gelling, ageing, washing can generate the radioactive wastewater largely containing substances such as ammonia, uranium, organic matter, nitrate.
High temperature gas cooled reactor 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, Tsinghua University's power English etc. has invented a kind of NH3-N
Recovery method (Quan Ying, Chen Xiaotong, Wang Yang, Liu Bing, Tang Yaping, NH in a kind of waste liquid containing ammonia3The recovery method of-N,
CN201310144190.X), which is distilled using intermittent warming treatment, fed-batch mode, and passes through cyclic absorption for waste liquid
In most of NH3- N is removed and is recycled, while also avoiding the evolution of radioactive element uranium, the removal of final ammonia
Rate is greater than 90%, and the concentration of ammonia is lower than 1% in liquid after processing.
For this radioactive liquid waste except after ammonia, Tsinghua University Chen Xiao is red etc., and to have invented a kind of wastewater treatment method (old
Know red, He Linfeng, Lu Zhenming, Liu Bing, Tang Yaping, the processing method of high temperature gas cooled reactor element core preparation process waste water,
CN201410546584.2), which removes organic matter, silica gel absorption uranium, reverse osmosis concentration using flocculation sedimentation, activated carbon adsorption
Etc. processes, can make processing after water outlet in uranium content be down to 0.05ppm or less.Although the uranium in waste liquid can be effectively removed in the method
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
(10ppm or less), waste liquid higher for uranium content, flocculating effect is bad, and the secondary concentrated water and silicon of reverse osmosis process generation
The secondary solids waste such as glue is more.
Summary of the invention
In view of this, the purpose of the present invention is to provide it is a kind of can to high uranium content high temperature gas cooled reactor fuel element production
The method that waste water is effectively treated, this method can efficiently recycle the uranium in waste liquid, and the COD of waste water is effectively reduced
Value, and process flow is short, secondary waste yield is few.
In order to achieve the above-mentioned object of the invention, the present invention the following technical schemes are provided:
A kind of processing method of high temperature gas cooled reactor fuel element production waste water, comprising the following steps:
The pH value of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8, filters, obtains after carrying out neutralization precipitation
To the first filtrate and filter cake, filtration cakes torrefaction is recycled；The mass content of ammonia in the high temperature gas cooled reactor 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 obtained by filtration
Liquid；
Second filtrate is subjected to activated carbon adsorption.
Preferably, the temperature of the neutralization precipitation is 60~100 DEG C；The time of the neutralization precipitation is 30~120min.
Preferably, the temperature of the complex-precipitation is 60~100 DEG C；The time of the complex-precipitation is 30~120min.
Preferably, the alkaline calcium compound is calcium oxide and/or calcium hydroxide.
Preferably, the quality of the alkaline calcium compound and the volume ratio of the first filtrate are 0.2~5g:1L.
Preferably, the phosphatic quality and the volume ratio of the first filtrate are 0.2~10g:1L.
Preferably, the phosphate is sodium phosphate, potassium phosphate, ammonium phosphate, dibastic sodium phosphate, potassium hydrogen phosphate, ammonium hydrogen phosphate, phosphorus
One or more of acid dihydride sodium, potassium dihydrogen phosphate and ammonium dihydrogen phosphate mixture.
Preferably, the activated carbon adsorption uses activated-charcoal column.
The present invention provides a kind of high temperature gas cooled reactor fuel element production wastewater treatment devices, 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
Water outlet be connected with the water inlet of neutralization-precipitation reaction kettle, the water outlet and the first plate compression of the neutralization-precipitation reaction kettle
The water inlet of machine is connected, and the water outlet of first plate and frame filter press is connected with the water inlet of complex-precipitation reaction kettle, the network
Close precipitation reaction kettle water outlet and the second plate and frame filter press water inlet be connected, the water outlet of second plate and frame filter press and
Activated-charcoal column water inlet is connected.
The present invention provides a kind of processing methods of high temperature gas cooled reactor fuel element production waste water, pass through neutralization precipitation, network
Precipitating and activated carbon adsorption are closed to handle high temperature gas cooled reactor fuel element production waste water, by neutralization precipitation by big portion exhausted in waste water
Divide uranium recycling, is removed uranium remaining in waste liquid by complex-precipitation and activated carbon adsorption, and pass through steps of activated carbon adsorption
The COD value of waste water is greatly reduced.Embodiment shows that method provided by the invention can be that 1~1000mg/L gives up to uranium content
Water is effectively treated, and 93.5% or more uranium can be recovered, and the uranium content after processing in water outlet is lower than 0.05ppm, COD value
For 100mg/L or so；And the secondary waste yield of the present invention is few, only generates a small amount of waste residue in complex-precipitation step, is suitble to scale
Change processing.
Detailed description of the invention
Fig. 1 is the schematic diagram of high temperature gas cooled reactor fuel element production wastewater treatment device of the present invention；
In Fig. 1: 1- waste liquid tank；2- neutralization-precipitation reaction kettle；The first plate and frame filter press of 3-；4- complex-precipitation reaction kettle；5-
Second plate and frame filter press；6- activated-charcoal column；7- pump.
Specific embodiment
The present invention provides a kind of processing methods of high temperature gas cooled reactor fuel element production waste water, comprising the following steps:
The pH of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8, filters, obtains after carrying out neutralization precipitation
First filtrate and filter cake, filtration cakes torrefaction is recycled；The mass content of ammonia is small in the high temperature gas cooled reactor 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 obtained by filtration
Liquid；
Second filtrate is subjected to activated carbon adsorption.
The pH value of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8 by the present invention, carries out mistake after neutralization precipitation
Filter, obtains the first filtrate and filter cake, filtration cakes torrefaction is recycled；The quality of ammonia in the high temperature gas cooled reactor 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 high temperature gas cooled reactor fuel element production waste water
In 2%, preferably less than it is equal to 1.5%.
The mass content of ammonia is about 17~25% in original high temperature gas cooled reactor fuel element production waste water, and a large amount of ammonia are deposited
In it will lead to and a large amount of acid is needed, consumption of raw materials is not only increased, but also a large amount of ammonium salts can be generated in the solution, influences subsequent place
Manage effect.Therefore, the process object of the method for the invention is except the high temperature gas cooled reactor fuel element after ammonia produces waste water, this hair
It is bright that it is preferable to use ammonia still process methods that the ammonia in waste water is evaporated off；The present invention does not have particular/special requirement to the detailed process of ammonia still process method, uses this
The ammonia still process method of field routine.
Convenient for statement, by this ammonia still process, treated that high temperature gas cooled reactor fuel element production waste water is known as in the present invention
High temperature gas cooled reactor fuel element produces waste water；In the present invention, the high temperature gas cooled reactor fuel element produces the COD value of waste water about
For 2000~10000mg/L, uranium content is about 1~1000ppm.
The pH value of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8, preferably 6.2~6.5 by the present invention,
More preferably 6.3~6.4.Present invention preferably uses acid solutions to adjust pH value；The acid solution is the mixture of concentrated acid and water；Institute
Stating concentrated acid is preferably one or more of sulfuric acid, hydrochloric acid and nitric acid, more preferably sulfuric 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, and more preferably 70~90 DEG C, most preferably
It is 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 rate of the stirring is preferably 150~300 turns/min,
More preferably 200~250 turns/min.
After the neutralization precipitation, the present invention will preferably filter after neutralization precipitation feed liquid cooled to room temperature, obtain 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, it preferably filters or plate compression, more preferably plate compression.
After obtaining filter cake, the present invention preferably recycles 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, 93.5% or more uranium is entered in filter cake by neutralization precipitation in waste liquid, the filter cake it is main at
It is divided into ammonium diuranate, wherein uranium content is 63% or more, and filter cake after the recovery can directly be used as through high-temperature roasting prepares high temperature
The raw material of air cooled reactor fuel element.
The present invention can be removed in waste water 93.5% or more uranium by neutralization precipitation, after neutralization precipitation is handled
To the first filtrate in uranium content be lower than 15ppm, COD value slightly reduce.
In alkalescent waste liquid containing ammonia, uranium is predominantly in the form of the biggish ammonium uranyl tricarbonate of solubility, the present invention
System is neutralized to subacidity by acid adding, so that ammonium uranyl tricarbonate is transformed into the smaller ammonium diuranate of solubility, to generate
Precipitating, while carbon dioxide is released, promote carbon dioxide to be discharged by heating, to further promote chemical reaction equilibrium to the right
It is mobile, make uranium precipitating more thoroughly, recycled so that most uranium be made to enter in filter cake, specific chemical reaction is such as 1 institute of formula
Show:
After obtaining the first filtrate, the present invention carries out complexing after mixing the first filtrate with alkaline calcium compound, phosphate heavy
It forms sediment, the second filtrate is obtained by filtration.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 of 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, and more preferably 70~90 DEG C, most preferably
It is 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 rate of the stirring is preferably 150~300 turns/min,
More preferably 200~250 turns/min.
The present invention is complexed using the uranium in phosphate radical and the first filtrate, and ultimately forms hydroxyl in conjunction with alkaline calcium compound
Apatite Ca5(PO4)3(OH), part uranyl ion is fixed on hydroxyapatite Ca5(PO4)3(OH) in lattice, simultaneously will
The surface and structure hole of part uranyl ion and remaining very tiny ammonium diuranate precipitating granular absorption in hydroxyapatite
In road, to achieve the purpose that further except uranium.
After the complex-precipitation, the present invention will preferably filter after complex-precipitation feed liquid cooled to room temperature, obtain second
Filtrate and filter residue.In the present invention, the method for the filtering is consistent with the filter method after neutralization precipitation, and details are not described herein；
Obtained filter residue can carry out curing process with cement, be transported to radiation solid waste repository storage.
The present invention can remove in the first filtrate 90% or more uranium, second obtained after complex-precipitation by complex-precipitation
Uranium content in filtrate is lower than 2ppm, and COD value slightly reduces in complex-precipitation step.
After obtaining the second filtrate, the second filtrate is preferably carried out activated carbon adsorption by the present invention.In the present invention, the activity
It is preferable to use activated-charcoal columns for charcoal absorption；In a specific embodiment of the present invention, the second filtrate can be made to flow through activity from bottom to top
Charcoal post, to guarantee optimal adsorption effect；Flow velocity of second filtrate in activated carbon adsorption 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；Activated carbon adsorption
It can be washed with dust technology after saturation, regeneration after drying.
High temperature gas cooled reactor fuel element produce waste water in, the organic matter containing glue, as tetrahydrofurfuryl alcohol, polyvinyl alcohol,
Six methines, four ammonium etc. has a small amount of uranium and these organic matters to form complex compound, is very by neutralization precipitation, phosphate complex-precipitation
Difficulty removes this part uranium；Huge surface area and abundant pore structure of the present invention using active carbon, and its it is smaller to polarity
The stronger characteristic of organic matter adsorption capacity, the uranium of organic matter and complex state in waste water is removed, is further decreased in waste water
Uranium content.
In the present invention, the uranium content in activated carbon adsorption water outlet is lower than 0.05ppm, and content of organics is in activated carbon adsorption
It is greatly lowered in step, the COD value of water outlet is only 100mg/L or so.
In the present invention, when the high temperature gas cooled reactor fuel element production Uranium in Waste Water content is more than or equal to 20ppm, pass through
Neutralization precipitation, complex-precipitation and three step of activated carbon adsorption are recycled and are removed to uranium, and drop the COD value of waste water substantially
It is low；When high temperature gas cooled reactor fuel element production Uranium in Waste Water content is lower than 20ppm, since uranium content is lower, it can omit
The step of with precipitating, directly carries out the removal of uranium by complex-precipitation and two step of activated carbon adsorption；In specific implementation of the invention
In example, suitable treatment process can be selected according to the composition of waste liquid.
The processing method of high temperature gas cooled reactor fuel element provided by the invention production waste water to the uranium in waste water and can have
Machine object is effectively removed, and the uranium content and COD value in water outlet are all up state specified standards, also contains one in water outlet
Quantitative salt (about 10~40g/L) will carry out natural evaporation concentration, no longer need to carry out other any places after effluent collection
Reason.
The present invention provides a kind of high temperature gas cooled reactor fuel element production wastewater treatment devices, 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
Water outlet be connected with the water inlet of neutralization-precipitation reaction kettle, the water outlet and the first plate compression of the neutralization-precipitation reaction kettle
The water inlet of machine is connected, and the water outlet of first plate and frame filter press is connected with the water inlet of complex-precipitation reaction kettle, the network
Close precipitation reaction kettle water outlet and the second plate and frame filter press water inlet be connected, the water outlet 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 1 water outlet of waste liquid tank 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 water outlet of the first plate and frame filter press is pumped into network
It closes precipitation reaction kettle 4 and carries 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,
The water outlet of second plate and frame filter press is pumped into activated-charcoal column 6 from bottom to top and carries out activated carbon adsorption, activated-charcoal column Chinese effluent to fuel
Concentration is evaporated in the element preparation dedicated Natural Evaporating Ponds To The Atmosphere of factory.
In the present invention, three neutralization precipitation, complex-precipitation and activated carbon adsorption step continuously-runnings, can also be only
Vertical operation can form according to waste liquid in a specific embodiment of the present invention and select the suitable method of operation.
It is carried out below with reference to processing method of the embodiment to high temperature gas cooled reactor fuel element provided by the invention production waste water
Detailed description, but they cannot 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, add sulfuric acid regulation system pH value to 6.3, system temperature is then heated to 85 DEG C, heat preservation 60min, after reaction, nature
It is cooled to room temperature, feed liquid is extracted out, plate compression obtains the first filtrate and filter cake；Uranium content in first filtrate is detected,
It is 12.32ppm that uranium content, which can be obtained, and uranium removal rate is up to 97.6%；Filter cake is dried and is recycled, filter cake quality 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 lime is added under agitation, is then added
System is heated to 80 DEG C, keeps the temperature 70min, after reaction, cooled to room temperature takes out feed liquid by 200g sodium dihydrogen phosphate
Out, plate compression obtains the second filtrate, and measuring uranium content in the second filtrate is 0.51ppm (510ppb), and uranium removal rate reaches
95.9%；Filter residue is temporary as secondary solid waste；
Second filtrate is pumped into activated-charcoal column from lower end, is discharged from activated-charcoal column upper end, water discharge speed about 1L/min is controlled,
To activated-charcoal column upper end be discharged carry out uranium content and COD value detection, must can be discharged in uranium content average value be 0.04ppm
(40ppb), COD value are reduced to 118mg/L from the 7520mg/L of initial waste liquid.
Uranium and COD content balance are shown in Table 1 in each section of feed liquid before and after the processing and in treatment process.
Table 1 uranium and COD content in each section of feed liquid before and after the processing and in treatment process
| 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 liquid (pH=9.5, uranium content 126.00ppm) is pumped into neutralization-precipitation reaction kettle, under agitation
Add nitric acid regulation system pH value to 6.5, system temperature is then heated to 85 DEG C, keeps the temperature 120min, it is after reaction, naturally cold
But to room temperature, feed liquid is extracted out, plate compression, obtains the first filtrate, measuring uranium content in the first filtrate is 7.28ppm, uranium removal
Rate is up to 94.2%；Filter cake is dried and is recycled, filter cake quality 18.5g, measuring uranium content in filter cake is 63.7%, and the uranium rate of recovery reaches
93.5%；
First filtrate is pumped into complex reaction kettle, 30g milk of lime is added under agitation, 100g phosphorus is then added
System is heated to 80 DEG C, keeps the temperature 120min, after reaction, cooled to room temperature extracts feed liquid out, sheet frame by sour hydrogen ammonium
Filters pressing obtains the second filtrate, and measuring in the second filtrate uranium content is 0.08ppm (80ppb), and uranium removal rate 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, is discharged from activated-charcoal column upper end, water discharge speed about 1L/min is controlled,
To activated-charcoal column upper end be discharged carry out uranium content and COD value detection, must can be discharged in uranium content average value be 0.03ppm
(30ppb), COD value are reduced to 130mg/L from the 8135mg/L of initial waste liquid.
Uranium and COD content balance are shown in Table 2 in each section of feed liquid before and after the processing and in treatment process.
Table 2 uranium and COD content in each section of feed liquid before and after the processing and in treatment process
| 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 liquid (pH=9.8, uranium content 2.67ppm) is pumped into complex-precipitation reaction kettle, under agitation,
30g milk of lime is added, 40g potassium hydrogen phosphate is then added, system is heated to 90 DEG C, keeps the temperature 120min, it is after reaction, natural
It is cooled to room temperature, feed liquid is extracted out, plate compression obtains filtrate, and measuring wherein uranium content is 0.04ppm (40ppb), uranium removal rate
Up to 98.5%；Filter residue is temporary as secondary solid waste；
Filtrate is pumped into activated-charcoal column from lower end, is discharged from activated-charcoal column upper end, water discharge speed about 1L/min, water outlet are 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 balance are shown in Table 3 in each section of feed liquid before and after the processing and in treatment process.
Table 3 uranium and COD content in each section of feed liquid before and after the processing and in treatment process
| 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 of high temperature gas cooled reactor fuel element production waste water provided by the invention can
The high temperature gas cooled reactor fuel element production waste water of high uranium content is effectively handled, wherein 93.5% or more uranium can obtain
To recycling, the uranium content in water outlet is lower than 0.05ppm, and COD value is reduced to 100 or so, and process flow is short, energy consumption compared with
Low, secondary waste yield is few, and operating cost is low, operational safety is high, can be suitble to scale processing with continuous operation.
The above is only a preferred embodiment of the present invention, it is noted that for the ordinary skill people of the art
For member, various improvements and modifications may be made without departing from the principle of the present invention, these improvements and modifications are also answered
It is considered as protection scope of the present invention.
Claims (8)
1. a kind of processing method of high temperature gas cooled reactor fuel element production waste water, which comprises the following steps:
The pH value of high temperature gas cooled reactor fuel element production waste water is adjusted to 6~6.8, is filtered after carrying out neutralization precipitation, obtains the
One filtrate and filter cake, filtration cakes torrefaction is recycled；The mass content of ammonia is less than in the high temperature gas cooled reactor 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 obtained by filtration；
Second filtrate is subjected to activated carbon adsorption.
2. the method according to claim 1, wherein the temperature of the neutralization precipitation is 60~100 DEG C；In described
Time with precipitating is 30~120min.
3. the method according to claim 1, wherein the temperature of the complex-precipitation is 60~100 DEG C；The network
The time for closing precipitating is 30~120min.
4. the method according to claim 1, wherein the alkaline calcium compound is calcium oxide and/or hydroxide
Calcium.
5. according to the method described in claim 4, it is characterized 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. the method according to claim 1, wherein the phosphatic quality and the volume ratio of the first filtrate are
0.2~10g:1L.
7. method according to claim 1 or 6, which is characterized in that the phosphate be sodium phosphate, potassium phosphate, ammonium phosphate,
One or more of dibastic sodium phosphate, potassium hydrogen phosphate, ammonium hydrogen phosphate, sodium dihydrogen phosphate, potassium dihydrogen phosphate and ammonium dihydrogen phosphate are mixed
Close object.
8. the method according to claim 1, wherein the activated carbon adsorption uses activated-charcoal column.
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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 |
| 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 |
| 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 |
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| CN104291489B (en) * | 2014-10-15 | 2015-12-02 | 清华大学 | The treatment process of high temperature gas-cooled Nuclear fuel core core preparation technology waste water |
| CN105448373B (en) * | 2015-11-06 | 2018-06-01 | 西南科技大学 | A kind of uranium-containing waste water with high salt or waste liquid quickly remove uranium salt reduction method |
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