CN103794260A - Evaporation treatment method for radioactive waste liquids of nuclear power plant - Google Patents
Evaporation treatment method for radioactive waste liquids of nuclear power plant Download PDFInfo
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Abstract
The invention discloses an evaporation treatment method for radioactive waste liquids of a nuclear power plant. The method includes the following steps: firstly, collecting and gathering various waste liquids; secondly, subjecting the waste liquids to evaporation treatment to form distillate and concentrate, and detecting radioactivity of the distillate and the concentrate; thirdly, when radioactivity detection results are lower than radioactive discharge standards, discharging the distillate, when boron concentration in the concentrate is detected to be up to solidification standards, discharging and solidifying the concentrate, and finishing evaporation; if the radioactivity detection results are equal or higher than the radioactive discharge standards and the boron concentration in the concentrate is detected to be less than 10000ppm, adding acid to stepwise regulate pH value of the concentrate to be below 7, and repeating the second and third steps till evaporation is finished. The method is simple in process, convenient to operate, and capable of greatly lowering radioactivity of the distillate to enable the radioactivity to be lower than the discharge standards.
Description
Technical field
The invention belongs to nuclear power station radioactive waste processing and disposal technical field, relate to a kind of disposal route of radioactive liquid waste, relate in particular to a kind of nuclear power station radioactive liquid waste evaporation process method.
Background technology
In nuclear power station operational process, can produce various waste liquids, often contain radiomaterial in waste liquid, this waste liquid can not arbitrarily discharge, and the waste liquid source of containing radiomaterial, with Daya Gulf nuclear power base
Di Ling Australia nuclear power station first phase is example, and main waste liquid source sees the following form 1:
Table 1 waste liquid source table
These waste liquids through filtration and desalination still do not meet emission request or chemicals when defective needs carry out evaporation process; Concentrated through heating, distillate discharge, concentrate solidifies.But distillate discharge need to reach control criterion: Daya Gulf nuclear power base radioactivity control criterion is 0.5MBq/m
3, can discharge lower than this numerical value, otherwise need to continue to process.But because the composition of radioactive liquid waste is complicated especially, make supplied materials characteristic more and more outstanding on the impact of evaporation efficiency.Some time, in the normal situation of equipment operational factor, there will be the situation that radioactive liquid waste evaporator effectiveness is low.
Conventionally, the evaporation effect of evaporation element adopts decontamination factor or decontamination factor to represent.The total decontamination factor of evaporation element equals decontamination factor and the each pallet+demister of ZE(of evaporator EV) the product of decontamination factor.The decontamination system of the design of the radioactivity evaporator in Daya Gulf nuclear power base is 10
-6due in actual motion, the discharge of waste liquid decides according to its radioactivity size, so for the ease of using, do not represent the effect of evaporation element with decontamination factor, but use radioactive liquid waste emission control standard, as weighing the quality of passing judgment on radioactivity evaporation element efficiency.The situation that evaporator distillate radioactivity is exceeded to control criterion, is all called evaporation element efficiency low.
According to analysis, cause the low possible factor of radioactivity evaporation element efficiency have following some: the atomizing effect of charging, the speed of steam (column evaporator and decontaminating column), condensate return amount (reflux ratio), the characteristic (as composition, concentration, volatility, foaming) of supplied materials, demister effect, operational factor.When radioactive liquid waste evaporator occurs in inefficient situation, the common way of nuclear power station is: subpunch is washed metallic sieve, then adjusted evaporation capacity, or repeated evaporation, or adds defoamer, and last way is that emptying evaporator concentrate carries out evaporator flushing.Generally, the distillate that exceedes control criterion can reach control criterion by these means.But still there will be after various means (concentrate again cannot be emptying), distillate still exceedes control criterion, situation that can not qualified discharge.For protection of the environment, normal operation or the overhaul in power station discharged or avoided affecting to the emission standard of avoiding distillate to exceed nuclear power plant inside, has to take concentrate is solidified in advance, and the measure that evaporator is rinsed guarantees the efficiency of evaporation element.Consequence is the solid waste that has increased nuclear power station, has increased high subsequent treatment cost.
Summary of the invention
The technical problem to be solved in the present invention is, occur in inefficient situation for radioactive liquid waste evaporator in prior art, adopt conventional flushing metallic sieve, adjust evaporation capacity, repeated evaporation, when adding the method such as defoamer, evaporator flushing and cannot solving the low defect of evaporator effectiveness, provide a kind of technique simple, easy to operate, can significantly reduce distillate radioactivity, make its nuclear power station radioactive liquid waste evaporation process method lower than emission standard.
The technical solution adopted for the present invention to solve the technical problems is: a kind of nuclear power station radioactive liquid waste evaporation process method, comprises the following steps:
(1), various waste collection are concentrated;
(2), waste liquid is carried out to evaporation process, form distillate and concentrate, distillate and concentrate are discharged to detection;
(3), be less than hot drain standard when the radiological measuring result of distillate, discharge distillate, detects concentrate and reaches while solidifying standard concentrate is discharged and solidified, and evaporation finishes;
When the radiological measuring result of distillate is equal to or greater than hot drain standard, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, progressively the pH value of concentrate is adjusted to below 7; Repeating step (2), (3) are until concentrate reaches curing standard, and evaporation finishes.
In described nuclear power station radioactive liquid waste evaporation process method, preferably include following steps:
(1) the various not reusable radioactive liquid waste, first nuclear power station being formed is collected in corresponding preposition waste liquid tank;
(2), the waste liquid in preposition waste liquid tank be delivered to evaporator carry out evaporation process, the steam of evaporation is delivered to condenser condenses and is formed distillate, being retained in evaporator is concentrate, and distillate and concentrate are discharged to detection;
(3), when the radioactivity that detects distillate is lower than hot drain standard 0.5MBq/m
3time discharge distillate; Detection concentrate reaches while solidifying standard discharges concentrate to solidify, evaporation end;
When the radioactivity that detects distillate is equal to or higher than hot drain standard 0.5MBq/m
3, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, by the pH value of concentrate progressively turn down to pH value be 5 ~ 7, then to being equal to or higher than 0.5MBq/m
3distillate add-back concentrate in, repeating step (2), (3) are until concentrate reaches curing standard, evaporation finishes.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), the amount of described acid adding is by adopting chemical titration to determine to concentrate.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), adopt the pH value of approximatioss acid adding reduction concentrate step by step.
In described nuclear power station radioactive liquid waste evaporation process method, described approximatioss is step by step: waste liquid is carried out the gradation of gradation acid adding and evaporates to regulate to the pH value of concentrate, each acid adding time is for before each evaporation starts; Often complete after an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend progressively reducing, and whether checking concentrate pH value is consistent with the testing result of chemistry titration.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), when acid adding, concentrate is sampled to detect and analyze, detect sodium boron ratio, boron content, total salinity in concentrate, described curing standard is that boron concentration reaches 40000-50000ppm, and in concentrate, sodium boron is cured concentrate when the 0.20-0.25 than (weight ratio); Or total salinity is cured concentrate after reaching 300g/L.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), in the time that the sodium boron ratio in testing result should be between 0.20-0.25, concentrate hydro-oxidation sodium is adjusted, made sodium boron ratio meet above-mentioned requirements.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), when acid adding, also need the gross activity of concentrate to carry out sample analysis, and the well heater RE shell-side temperature variation of evaporator is followed the tracks of.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), institute's acid adding is nitric acid.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (2), distillate radiological measuring frequency is that before each distillate discharge, sampling detects.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), the sampling of concentrate detects frequency and sample detection after often completing an acid adding operation.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), pH value if the well heater RE shell-side temperature of evaporator exceedes 137 ℃, needs evaporator to clean after adjusting.
The present invention adopts in evaporation process after all waste collection, monitoring distillate radioactivity, when radiological measuring result is less than hot drain standard, discharge distillate, concentrate is discharged after boron concentration reaches curing standard (40000-50000ppm) or total salinity to reach 300g/L time and is solidified; When radiological measuring result is equal to or greater than hot drain standard, acid adding regulates the pH value of concentrate, then the distillate that is equal to or higher than hot drain standard is evaporated.Acid adding can be improved evaporation efficiency, and reason has three: one, and concentrate is acidity can reduce the height that evaporator foams effectively, reduces carrying secretly in evaporation process; The 2nd, " pickling " of acidic materials makes contaminated CS/ZE(condenser and clarifier) be purified; The 3rd, acid adding has changed concentrate radiomaterial form, as the radioactive material of some colloidal attitude has been changed into ionic state, or chemical reaction formation not volatile " deposition " occurs, and has also reduced the possibility of carrying secretly.From analysis data, the situation of change of boron concentration shows that boron does not participate in " deposition ", and the harmful effect maximum of boron crystallization to system.
The invention provides a kind of effective new method of improving evaporator effectiveness that need not emptying evaporator concentrate, normal in equipment operational factor, when evaporator occurs that efficiency is low, in the situation that original various means except emptying still can not be qualified, by controlling the method for evaporator concentrate pH value, successfully solve inefficient problem.In the situation that using other means invalid (as adding defoamer, adjust operation parameter), the present invention successfully uses 3 times at ridge Australia first phase nuclear power station, each use can make the radioactive level of the distillate of evaporator reach below instrument detection line, is all less than 0.2MBq/m
3.The radioactive liquid waste of guaranteeing has obtained processing timely and effectively, has guaranteed carrying out smoothly of major overhaul state, has avoided the discharge beyond standards causing not in time due to liquid waste processing and has delayed thus the economic loss that overhaul critical path causes.
Accompanying drawing explanation
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing:
Fig. 1 is evaporation element structure and process flow diagram thereof;
Fig. 2 is pH value and the distillate radioactive relationship figure of the embodiment of the present invention.
Embodiment
A kind of nuclear power station radioactive liquid waste evaporation process method, comprises the following steps:
(1), various waste collection are concentrated;
(2), waste liquid is carried out to evaporation process, form distillate and concentrate, distillate and concentrate are discharged to detection;
(3), be less than hot drain standard when the radiological measuring result of distillate, discharge distillate, detects concentrate and reaches while solidifying standard concentrate is discharged and solidified, and evaporation finishes;
When the radiological measuring result of distillate is equal to or greater than hot drain standard, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, progressively the pH value of concentrate is adjusted to below 7; Repeating step (2), (3) are until concentrate reaches curing standard, and evaporation finishes.
In described nuclear power station radioactive liquid waste evaporation process method, preferably include following steps:
(1) the various not reusable radioactive liquid waste, first nuclear power station being formed is collected in corresponding preposition waste liquid tank;
(2), the waste liquid in preposition waste liquid tank be delivered to evaporator carry out evaporation process, the steam of evaporation is delivered to condenser condenses and is formed distillate, being retained in evaporator is concentrate, and distillate and concentrate are discharged to detection;
(3), when the radioactivity that detects distillate is lower than hot drain standard 0.5MBq/m
3time discharge distillate; Detection concentrate reaches while solidifying standard discharges concentrate to solidify, evaporation end;
When the radioactivity that detects distillate is equal to or higher than hot drain standard 0.5MBq/m
3, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, by the pH value of concentrate progressively turn down to pH value be 5 ~ 7, then to being equal to or higher than 0.5MBq/m
3distillate add-back concentrate in, repeating step (2), (3) are until concentrate reaches curing standard, evaporation finishes.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), the amount of described acid adding is by adopting chemical titration to determine to concentrate.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), adopt the pH value of approximatioss acid adding reduction concentrate step by step.
In described nuclear power station radioactive liquid waste evaporation process method, described approximatioss is step by step: waste liquid is carried out the gradation of gradation acid adding and evaporates to regulate to the pH value of concentrate, each acid adding time is for before each evaporation starts; Often complete after an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend progressively reducing, and whether checking concentrate pH value is consistent with the testing result of chemistry titration.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), when acid adding, concentrate is sampled to detect and analyze, detect sodium boron ratio, boron content, total salinity in concentrate, described curing standard is that boron concentration reaches 40000-50000ppm, and in concentrate, sodium boron is cured concentrate when the 0.20-0.25 than (weight ratio); Or total salinity is cured concentrate after reaching 300g/L.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), in the time that the sodium boron ratio in testing result should be between 0.20-0.25, concentrate hydro-oxidation sodium is adjusted, made sodium boron ratio meet above-mentioned requirements.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), when acid adding, also need the gross activity of concentrate to carry out sample analysis, and the well heater RE shell-side temperature variation of evaporator is followed the tracks of.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), institute's acid adding is nitric acid.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (2), distillate radiological measuring frequency is that before each distillate discharge, sampling detects.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), the sampling of concentrate detects frequency and sample detection after often completing an acid adding operation.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), pH value if the well heater shell-side temperature of evaporator exceedes 137 ℃, needs evaporator to clean after adjusting.
(1) the various not reusable radioactive liquid waste, first nuclear power station being formed is collected in corresponding preposition waste liquid tank;
(2), the waste liquid in preposition waste liquid tank be delivered to evaporator carry out evaporation process, the steam of evaporation is delivered to condenser condenses and is formed distillate, being retained in evaporator is concentrate, detects the radioactivity of distillate; In described step (2), distillate radiological measuring frequency is that before each distillate discharge, sampling detects.
(3) radioactivity that, detects distillate is lower than 0.5MBq/m
3time discharge distillate; The radioactivity that detects distillate is equal to or higher than 0.5MBq/m
3time, and detect boron concentration in concentrate and be less than 10000ppm, acid adding is progressively turned down the pH value of concentrate, to pH value be 5 ~ 7, then to being equal to or higher than 0.5MBq/m
3distillate re-start evaporation, and detect its radioactivity.Wherein institute's acid adding is nitric acid, and acid adding amount is to adopt chemical titration to determine to concentrate.The sampling of concentrate detects frequency and sample detection after often completing an acid adding operation.Adopt the pH value of approximatioss acid adding reduction concentrate step by step.Described approximatioss is step by step: waste liquid is carried out the gradation of gradation acid adding and evaporates to regulate to the pH value of concentrate, each acid adding time is for before each evaporation starts; Often complete after an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend progressively reducing, and whether checking concentrate pH value is consistent with the result of chemistry titration.
When acid adding, concentrate is sampled to detect and analyze, detect sodium boron ratio, boron content in concentrate, wherein the sodium boron ratio in testing result should meet between 0.20-0.25, otherwise concentrate is added to alkali adjustment, makes sodium boron ratio meet above-mentioned requirements.Total salinity, gross activity to concentrate are carried out sample analysis, and the well heater RE shell-side temperature variation of evaporator is followed the tracks of.
PH value if the well heater RE shell-side temperature of evaporator exceedes 137 ℃, needs evaporator to clean after adjusting.
(4), repeating step (2), (3) are until evaporation end.
1, November 9, occur that in ridge Australia first phase nuclear power station waste liquid evaporation element (L9TEU) efficiency is low.In the processing procedure of use conventional method, when on-the-spot discovery condenser CS sampling, there are a large amount of foams to produce, therefore suspect that the low foam with waste liquid in evaporator EV of efficiency is excessive relevant, since to 2007, in the investigation of relevant evaporation activity, found simultaneously, every secondary evaporator EV adds alkali and adjusts after the Na/B of evaporator EV concentrate, the efficiency of evaporator EV all there will be this general character phenomenon of super inner quality standard, and the concentrate pH value of the evaporator EV of ridge Australia first phase nuclear power station is 8.5, than Daya Bay nuclear power plant's 6.3 height, confirm that by overtesting evaporator EV concentrate bubbles serious.Use defoamer also the efficiency of evaporator EV cannot be processed to the inner quality standard 0.5MBq/m that meets power station
3in.Therefore, three wastes group of power plant determines first to start with from the pH that adjusts concentrate, and it adjusts bottom line is the pH value 6.3 that is no more than Daya Bay nuclear power plant, to attempt whether can improving the efficiency of evaporator EV.
November 24, complete after acid adding for the first time (we use be the industrial nitric acid that the conventional concentration in power station is 55%).Evaporator EV concentrate pH value has dropped to 7.0 by 8.4, and in acid adding process, the sampling result of condenser CS has progressively been dropped to and has been less than 0.2MBq/m by initial 1.05MBq/m3
3, be less than inner quality standard 0.5MBq/m
3.Reach expection requirement.
Completed November 27 after concentrate passback, it is large that the γ level of condenser CS becomes, and the pH value of condenser CS raises, consistent with expection; PH value in evaporator EV is substantially constant, and radioactivity is also than original little a lot, larger with original expection difference, thinks that the radiomaterial in former evaporator EV deposits to the reason of residue.
November 29, determines again to turn down concentrate pH value, in order to control risk, first the pH value of evaporator EV concentrate is adjusted to 6.8 by 7.0.
Dec, 1-2 day, completed acid adding, and the acid adding amount of expectation is 50L, and reality has approximately added 42L.The pH value of last evaporator EV concentrate has dropped to 6.34 by 7.04.γ=the 5.4MBq/m of the sampling result of condenser CS before by acid adding
3, dropped to and be less than 0.2MBq/m
3, the γ=50257MBq/m of evaporator EV concentrate
3, than (γ=7343MBq/m before acid adding
3) significantly increase, think that intrasystem radiomaterial got off by pickling due to.
Dec 5, the sampling result of evaporator EV finds that the γ of concentrate has declined to a great extent 4264
MBq/m
3, dropped to 1566MBq/m while again sampling on Dec 6
3.Dec 10 was 888MBq/m
3, and concentrate color obviously shoals, from before brownish black become khaki, insoluble matter obviously reduces, and suspects that possible cause that radioactivity reduces is radiomaterial as silver etc. and other impurity (calcium, magnesium, silicon, phosphate, organism etc.) there is together the phenomenons such as precipitation, absorption.Confirm that boron does not participate in deposition process.
Complete and add alkali work, the sampling result of evaporator EV morning Dec 12: the radioactivity of concentrate has gone back up to 3963MBq/m
3.Na/B=0.217, has reached expection.The still γ < 0.2MBq/m of state 5 sampling results of condenser CS
3, the detersive efficiency of evaporator EV is there are no degradating trend.
Dec 14, the overstandard waste water of L9TEU03/04/016BA was all disposed (about 110m3), the equal γ < of sampling result 0.2MBq/m by 19 days
3.The L9TEU001 evaporator EV gross activity of 19 days is 27981MBq/m
3significantly go up, concentrate color is more obvious the deepening than last time also, sample has a little precipitation, in conjunction with the contact agent dose rate of Radiation monitoring point decline (by maximum time 5.8 drop to 2.6mSv/h) and the 9TEU-RE thermal efficiency rise (104MT has dropped to 106 degree by 117 degree) judge, there is reversible situation in L9TEU001 evaporator EV sediment.
Adjust in concentrate pH value process, the radioactivity situation of change of condenser CS distillate as shown in Figure 2.
Three, the laboratory simulation test of different pH to concentrate deposition affects:
Process of the test and the results are shown in following table 2:
The different pH of table 2 affect process of the test and result to concentrate
Conclusion: it is relatively good that test findings is coincide with on-site actual situations.By the variation of pH, deposition presents reversible phenomenon.
As shown in Figure 1, Fig. 1 is evaporation element structure and process flow diagram thereof to evaporation equipment.The major equipment that is shown in the liquid waste treatment system evaporation element of installing in nuclear auxiliary building in Fig. 1 is as follows:
A well heater (001RE), the supply that it has guaranteed to heat the auxiliary steam flow of concentrate.
An evaporation pillar (001EV), the release of overheated concentrate occurs in this device.Gravity separation for the first time between steam and the concentrate of incidental impurities that this device has guaranteed to produce.The fundamental purpose of the atomizing spray of charging waste liquid is eliminate the steam that causes of concentrate overheated.By embedding and the diluting effect of dropping liquid forming, it also assists in removing radioactive pollution.
Purification (removing an alpha-contamination) pillar (001ZE), is received within the lower at pillar from the steam of evaporation pillar.Alpha-contamination removal guarantees by following means:
By slip out from a part for condenser that circulation that thing and steam intersects carries out run through 3 pallets time steam flushing (backflows), reflux ratio is confirmed as 20% normally.
A metallic sieve of the mixing forming through the factor of porosity being successively decreased by 3 layer thicknesses carries out last demist.
A reflux condenser (001CS), it has guaranteed the condensation of the steam being cleaned that carrys out self-purification (removal is polluted) pillar by the chilled water in tube exterior circulation.
A forced circulation pump (006PO), it is a centrifugal pump of horizontal axis.Its feature is: low head, large flow.Its use is the circulation of guaranteeing to evaporate pillar, well heater and turning back to concentrate between evaporation pillar; Wash away circulation line simultaneously, concentrate is had to certain heat effect, to avoid the crystallization of evaporation circuit boron.
Claims (12)
1. a nuclear power station radioactive liquid waste evaporation process method, is characterized in that, comprises the following steps:
(1), various waste collection are concentrated;
(2), waste liquid is carried out to evaporation process, form distillate and concentrate, distillate and concentrate are discharged to detection;
(3), be less than hot drain standard when the radiological measuring result of distillate, discharge distillate, detects concentrate and reaches while solidifying standard concentrate is discharged and solidified, and evaporation finishes;
When the radiological measuring result of distillate is equal to or greater than hot drain standard, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, progressively the pH value of concentrate is adjusted to below 7; Repeating step (2), (3) are until concentrate reaches curing standard, and evaporation finishes.
2. nuclear power station radioactive liquid waste evaporation process method according to claim 1, is characterized in that, comprises the following steps:
(1) the various not reusable radioactive liquid waste, first nuclear power station being formed is collected in corresponding preposition waste liquid tank;
(2), the waste liquid in preposition waste liquid tank be delivered to evaporator carry out evaporation process, the steam of evaporation is delivered to condenser condenses and is formed distillate, being retained in evaporator is concentrate, and distillate and concentrate are discharged to detection;
(3), when the radioactivity that detects distillate is lower than hot drain standard 0.5MBq/m
3time discharge distillate; Detection concentrate reaches while solidifying standard discharges concentrate to solidify, evaporation end;
When the radioactivity that detects distillate is equal to or higher than hot drain standard 0.5MBq/m
3, and detect in concentrate when boron concentration is less than 10000ppm, carry out step (4);
(4), in concentrate acid adding, by the pH value of concentrate progressively turn down to pH value be 5 ~ 7, then to being equal to or higher than 0.5MBq/m
3distillate add-back concentrate in, repeating step (2), (3) are until concentrate reaches curing standard, evaporation finishes.
3. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, is characterized in that, in step (3), the amount of described acid adding is by adopting chemical titration to determine to concentrate.
4. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, is characterized in that, in step (3), adopts the pH value of approximatioss acid adding reduction concentrate step by step.
5. nuclear power station radioactive liquid waste evaporation process method according to claim 4, is characterized in that, described approximatioss is step by step: waste liquid is carried out the gradation of gradation acid adding and evaporates to regulate to the pH value of concentrate, each acid adding time is for before each evaporation starts; Often complete after an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend progressively reducing, and whether checking concentrate pH value is consistent with the testing result of chemistry titration.
6. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, it is characterized in that, in step (3), when acid adding, concentrate is sampled to detect and analyze, detect sodium boron ratio, boron content, total salinity in concentrate, described curing standard is that boron concentration reaches 40000-50000ppm, and in concentrate, sodium boron is cured concentrate during for 0.20-0.25 than (weight ratio); Or total salinity is cured concentrate after reaching 300g/L.
7. nuclear power station radioactive liquid waste evaporation process method according to claim 6, it is characterized in that, in step (3), in the time that the sodium boron ratio in testing result should be between 0.20-0.25, concentrate hydro-oxidation sodium is adjusted, made sodium boron ratio meet above-mentioned requirements.
8. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, it is characterized in that, in described step (3), when acid adding, also need the gross activity of concentrate to carry out sample analysis, and the well heater shell-side temperature variation of evaporator is followed the tracks of.
9. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, is characterized in that, in described step (3), institute's acid adding is nitric acid.
10. nuclear power station radioactive liquid waste evaporation process method according to claim 1 and 2, is characterized in that, in described step (2), distillate radiological measuring frequency is that before each distillate discharge, sampling detects.
11. nuclear power station radioactive liquid waste evaporation process methods according to claim 1 and 2, is characterized in that, in described step (3), the sampling of concentrate detects frequency and sample detection after often completing an acid adding operation.
12. nuclear power station radioactive liquid waste evaporation process methods according to claim 1 and 2, is characterized in that, in described step (3), pH value if the well heater RE shell-side temperature of evaporator exceedes 137 ℃, needs evaporator to clean after adjusting.
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| CN114014397A (en) * | 2021-11-05 | 2022-02-08 | 中国船舶重工集团公司第七一八研究所 | System for testing heat pump evaporation device, method, equipment and medium thereof |
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| CN104810071A (en) * | 2015-04-16 | 2015-07-29 | 湖南桃花江核电有限公司 | Method and equipment for deep purifying of boron-containing radioactive waste liquid and recovery of boric acid |
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| CN108062990B (en) * | 2018-01-11 | 2024-06-07 | 航天晨光股份有限公司 | Radioactive waste liquid crystallization drying system and method thereof |
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| CN111312423A (en) * | 2020-02-19 | 2020-06-19 | 中国核动力研究设计院 | Radioactive boron-containing waste liquid concentration device |
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| CN112509721A (en) * | 2020-11-30 | 2021-03-16 | 湖南汉华京电清洁能源科技有限公司 | Radioactive sample processing method and device |
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| CN114014397A (en) * | 2021-11-05 | 2022-02-08 | 中国船舶重工集团公司第七一八研究所 | System for testing heat pump evaporation device, method, equipment and medium thereof |
| CN115798768A (en) * | 2023-01-04 | 2023-03-14 | 中国原子能科学研究院 | Radioactive waste liquid treatment method and system |
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