CN103794260B - Nuclear power station radioactive liquid waste evaporation process method - Google Patents
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- CN103794260B CN103794260B CN201210428266.7A CN201210428266A CN103794260B CN 103794260 B CN103794260 B CN 103794260B CN 201210428266 A CN201210428266 A CN 201210428266A CN 103794260 B CN103794260 B CN 103794260B
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Abstract
The invention discloses a kind of nuclear power station radioactive liquid waste evaporation process method, comprise the following steps: (1), various waste collection are concentrated；(2), to waste liquid it is evaporated processing, forms distillate and concentrated solution, the radioactivity of detection distillate and concentrated solution；(3), when radiological measuring result is less than hot drain standard, discharging distillate, discharged by concentrated solution and solidify when the boron concentration in detection concentrated solution reaches solidification standard, evaporation terminates；When radiological measuring result is equal to or more than hot drain standard, and when in detection concentrated solution, boron concentration is less than 10000ppm, the pH value of concentrated solution is progressively adjusted to less than 7 by acid adding；Repeat step (2), (3) until evaporation terminates.The present invention provides one, and technique is simple, easy to operate, distillate radioactivity can be greatly lowered so that it is lower than the nuclear power station radioactive liquid waste evaporation process method of discharge standard.
Description
Technical field
The invention belongs to nuclear power station radioactive waste processing and disposal technical field, relate to the processing method of a kind of radioactive liquid waste, particularly relate to a kind of nuclear power station radioactive liquid waste evaporation process method.
Background technology
In nuclear power station running, producing various waste liquid, often containing radioactive substance in waste liquid, this waste liquid can not arbitrarily discharge, and the waste liquid containing radioactive substance is originated, with Daya Gulf nuclear power base
Ground Ling'ao nuclear power plant one phase is example, and table 1 below is seen in main waste liquid source:
Table 1 waste liquid source table
These waste liquids need to be evaporated processing when filtration and desalination are still unsatisfactory for emission request or chemicals are defective；Through heating concentration, distillate discharges, and concentrated solution solidifies.But distillate discharge needs reach control standard: it is 0.5MBq/m that Daya Gulf nuclear power base radioactivity controls standard3, can discharge lower than this numerical value, otherwise need to continue with.But owing to the composition of radioactive liquid waste is especially complex so that supplied materials characteristic is more and more prominent on the impact of evaporation efficiency.Some time, in the normal situation of equipment operational factor, it may appear that the situation that radioactive liquid waste evaporator effectiveness is low.
Generally, the evaporation effect of evaporation element adopts decontamination factor or decontamination factor to represent.The evaporation element total decontamination factor decontamination factor equal to vaporizer EV and each pallet+demister of ZE() the product of decontamination factor.The decontamination system of the design of the radioactivity vaporizer in Daya Gulf nuclear power base is 10-6, owing to, in actual motion, the discharge of waste liquid determines according to its radioactivity size, so for the ease of using, do not use decontamination factor to represent the effect of evaporation element, but use radioactive liquid waste emission control standard, as weighing the quality passing judgment on radioactivity evaporation element efficiency.Vaporizer distillate radioactivity is exceeded the situation of control standard, be all called evaporation element efficiency low.
According to analysis, cause the radioactivity low possible factor of evaporation element efficiency have following some: the atomizing effect of charging, the speed (column evaporator and decontaminating column) of steam, condensate return amount (reflux ratio), the characteristic (such as composition, concentration, volatility, foaming) of supplied materials, demister effect, operational factor.When radioactive liquid waste vaporizer occurs in inefficient situation, nuclear power station common practice is: first rinses metallic sieve, then adjust evaporation capacity or repeated evaporation, or adds defoamer, and last way is that emptying vaporizer concentrated solution is evaporated device and rinses.Generally, the distillate exceeding control standard can reach control standard by these means.But still there will be after various means (concentrated solution cannot empty again), distillate is still above controlling standard, it is impossible to the situation of qualified discharge.In order to protect environment, it is to avoid distillate exceedes the discharge standard discharge within nuclear power plant or avoids affecting the properly functioning of power station or overhaul, it has to taking concentrated solution premature cure, the measure that vaporizer is rinsed is to ensure the efficiency of evaporation element.Consequence is the increase in the solid waste of nuclear power station, adds high subsequent treatment cost.
Summary of the invention
The technical problem to be solved in the present invention is in that, occur in inefficient situation for radioactive liquid waste vaporizer in prior art, adopt conventional rinse metallic sieve, adjust evaporation capacity, repeated evaporation, when adding the method such as defoamer, vaporizer flushing and cannot solve the low defect of evaporator effectiveness, technique is simple, easy to operate, distillate radioactivity can be greatly lowered to provide one so that it is lower than the nuclear power station radioactive liquid waste evaporation process method of discharge 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), to waste liquid it is evaporated processing, forms distillate and concentrated solution, distillate and concentrated solution are carried out discharge detection；
(3), when the radiological measuring result of distillate is less than hot drain standard, discharging distillate, discharged by concentrated solution and solidify when detection concentrated solution reaches solidification standard, evaporation terminates；
When the radiological measuring result of distillate is equal to or more than hot drain standard, and when boron concentration is less than 10000ppm in detection concentrated solution, carry out step (4)；
(4), in concentrated solution acid adding, progressively the pH value of concentrated solution is adjusted to less than 7；Repeating step (2), (3) until concentrated solution reaches solidification standard, evaporation terminates.
In described nuclear power station radioactive liquid waste evaporation process method, it is preferable that comprise the following steps:
(1), first the various not reusable radioactive liquid waste that nuclear power station is formed is collected in corresponding preposition waste liquid tank；
(2), by the waste liquid in preposition waste liquid tank being delivered to vaporizer to be evaporated processing, the steam of evaporation is delivered to condenser condensation and is formed distillate, and being retained in vaporizer is concentrated solution, and distillate and concentrated solution carry out discharge detection；
(3), when the radioactivity of detection distillate is lower than hot drain standard 0.5MBq/m3Time discharge distillate；Being discharged by concentrated solution when detection concentrated solution reaches solidification standard and solidify, evaporation terminates；
When the radioactivity of detection distillate is equal to or higher than hot drain standard 0.5MBq/m3, and when boron concentration is less than 10000ppm in detection concentrated solution, carry out step (4)；
(4), in concentrated solution acid adding, the pH value of concentrated solution is progressively turned down to pH value be 5 ~ 7, then to equal to or higher than 0.5MBq/m3Distillate add-back concentrated solution in, repeat step (2), (3) until concentrated solution reaches solidification standard, evaporation terminates.
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 concentrated solution.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), approximatioss acid adding step by step is adopted to reduce the pH value of concentrated solution.
In described nuclear power station radioactive liquid waste evaporation process method, described approximatioss step by step is: waste liquid carrying out gradation acid adding gradation evaporation and regulates the pH value of concentrated solution, each acid addition time is for before evaporation starts every time；After often completing an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend gradually reduced, and verifies the whether consistent with the testing result of chemistry titration of concentrated solution pH value.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), during acid adding, concentrated solution is sampled detection analyze, sodium boron ratio in detection concentrated solution, Boron contents, total salinity, described solidification standard is that boron concentration reaches 40000-50000ppm, and in concentrated solution sodium boron ratio (weight ratio) for 0.20-0.25 time concentrated solution is solidified；Or total salinity reach 300g/L after concentrated solution is solidified.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), when the sodium boron ratio in testing result should not between 0.20-0.25 time, concentrated solution hydro-oxidation sodium is adjusted, makes sodium boron ratio meet above-mentioned requirements.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), during acid adding, also need to be sampled the gross activity of concentrated solution analyzing, and the heater RE shell-side variations in temperature of vaporizer is tracked.
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 sampling detection before the discharge of each distillate.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), the sampling detection frequency of concentrated solution detects for sampling 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 heater RE shell-side temperature of vaporizer is more than 137 DEG C, then needs vaporizer is carried out 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, discharging distillate, concentrated solution discharges solidification when boron concentration reaches solidification standard (40000-50000ppm) or total salinity reaches after 300g/L；When radiological measuring result is equal to or more than hot drain standard, acid adding regulates the pH value of concentrated solution, then is evaporated equal to or higher than the distillate of hot drain standard.Acid adding can improve evaporation efficiency, and reason has three: one to be concentrated solution be acidity can efficiently reduce the height of vaporizer foaming, reduces carrying secretly in evaporation process；Two is that acidic materials " pickling " make contaminated CS/ZE(condenser and depurator) it is purified；Three is that acid adding changes concentrated solution radioactive substance form, and the radioactive substance such as some colloidal attitude becomes ionic state, or occurs chemical reaction to form not volatile " deposition ", also reduces the possibility carried secretly.From analysis data, the situation of change of boron concentration shows that boron is not engaged in " deposition ", and boron crystallization is maximum to the harmful effect of system.
The invention provides a kind of new method being effectively improved evaporator effectiveness that need not empty vaporizer concentrated solution, normal in equipment operational factor, when vaporizer occurs that efficiency is low, original except emptying except various means still can not qualified when, by the method controlling vaporizer concentrated solution pH value, successfully solve inefficient problem.When using other means invalid (as add defoamer, adjust operational factor), the present invention successfully uses 3 times at ridge Australia one phase nuclear power station, use the radioactive level of the distillate that can make vaporizer to reach below instrument detection line every time, be namely both less than 0.2MBq/m3.The radioactive liquid waste guaranteed obtains and processes timely and effectively, it is ensured that being smoothed out of major overhaul state, it is to avoid the discharge beyond standards that causes not in time due to liquid waste processing and thus delayed 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 flow chart thereof；
Fig. 2 is pH value and the distillate radioactive relationship figure of the embodiment of the present invention.
Detailed description of the invention
A kind of nuclear power station radioactive liquid waste evaporation process method, comprises the following steps:
(1), various waste collection are concentrated；
(2), to waste liquid it is evaporated processing, forms distillate and concentrated solution, distillate and concentrated solution are carried out discharge detection；
(3), when the radiological measuring result of distillate is less than hot drain standard, discharging distillate, discharged by concentrated solution and solidify when detection concentrated solution reaches solidification standard, evaporation terminates；
When the radiological measuring result of distillate is equal to or more than hot drain standard, and when boron concentration is less than 10000ppm in detection concentrated solution, carry out step (4)；
(4), in concentrated solution acid adding, progressively the pH value of concentrated solution is adjusted to less than 7；Repeating step (2), (3) until concentrated solution reaches solidification standard, evaporation terminates.
In described nuclear power station radioactive liquid waste evaporation process method, it is preferable that comprise the following steps:
(1), first the various not reusable radioactive liquid waste that nuclear power station is formed is collected in corresponding preposition waste liquid tank；
(2), by the waste liquid in preposition waste liquid tank being delivered to vaporizer to be evaporated processing, the steam of evaporation is delivered to condenser condensation and is formed distillate, and being retained in vaporizer is concentrated solution, and distillate and concentrated solution carry out discharge detection；
(3), when the radioactivity of detection distillate is lower than hot drain standard 0.5MBq/m3Time discharge distillate；Being discharged by concentrated solution when detection concentrated solution reaches solidification standard and solidify, evaporation terminates；
When the radioactivity of detection distillate is equal to or higher than hot drain standard 0.5MBq/m3, and when boron concentration is less than 10000ppm in detection concentrated solution, carry out step (4)；
(4), in concentrated solution acid adding, the pH value of concentrated solution is progressively turned down to pH value be 5 ~ 7, then to equal to or higher than 0.5MBq/m3Distillate add-back concentrated solution in, repeat step (2), (3) until concentrated solution reaches solidification standard, evaporation terminates.
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 concentrated solution.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), approximatioss acid adding step by step is adopted to reduce the pH value of concentrated solution.
In described nuclear power station radioactive liquid waste evaporation process method, described approximatioss step by step is: waste liquid carrying out gradation acid adding gradation evaporation and regulates the pH value of concentrated solution, each acid addition time is for before evaporation starts every time；After often completing an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend gradually reduced, and verifies the whether consistent with the testing result of chemistry titration of concentrated solution pH value.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), during acid adding, concentrated solution is sampled detection analyze, sodium boron ratio in detection concentrated solution, Boron contents, total salinity, described solidification standard is that boron concentration reaches 40000-50000ppm, and in concentrated solution sodium boron ratio (weight ratio) for 0.20-0.25 time concentrated solution is solidified；Or total salinity reach 300g/L after concentrated solution is solidified.
In described nuclear power station radioactive liquid waste evaporation process method, in step (3), when the sodium boron ratio in testing result should not between 0.20-0.25 time, concentrated solution hydro-oxidation sodium is adjusted, makes sodium boron ratio meet above-mentioned requirements.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), during acid adding, also need to be sampled the gross activity of concentrated solution analyzing, and the heater RE shell-side variations in temperature of vaporizer is tracked.
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 sampling detection before the discharge of each distillate.
In described nuclear power station radioactive liquid waste evaporation process method, in described step (3), the sampling detection frequency of concentrated solution detects for sampling 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 heater shell-side temperature of vaporizer is more than 137 DEG C, then needs vaporizer is carried out after adjusting.
Embodiment 1, nuclear power station radioactive liquid waste evaporation process method, it is preferable that comprise the following steps:
(1), first the various not reusable radioactive liquid waste that nuclear power station is formed is collected in corresponding preposition waste liquid tank；
(2), by the waste liquid in preposition waste liquid tank being delivered to vaporizer to be evaporated processing, the steam of evaporation is delivered to condenser condensation and is formed distillate, is retained in vaporizer for concentrated solution, the radioactivity of detection distillate；In described step (2), distillate radiological measuring frequency is sampling detection before the discharge of each distillate.
(3) radioactivity of distillate, is detected lower than 0.5MBq/m3Time discharge distillate；The radioactivity of detection distillate is equal to or higher than 0.5MBq/m3Time, and in detection concentrated solution, boron concentration is less than 10000ppm, the pH value of concentrated solution is progressively turned down by acid adding, is 5 ~ 7 to pH value, then to equal to or higher than 0.5MBq/m3Distillate 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 concentrated solution.The sampling detection frequency of concentrated solution detects for sampling after often completing an acid adding operation.Approximatioss acid adding step by step is adopted to reduce the pH value of concentrated solution.Described approximatioss step by step is: waste liquid carrying out gradation acid adding gradation evaporation and regulates the pH value of concentrated solution, each acid addition time is for before evaporation starts every time；After often completing an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend gradually reduced, and verifies the whether consistent with the result of chemistry titration of concentrated solution pH value.
During acid adding, concentrated solution being sampled detection and analyzes, the sodium boron ratio in detection concentrated solution, Boron contents, wherein the sodium boron ratio in testing result should meet between 0.20-0.25, otherwise concentrated solution is added alkali and is adjusted, and makes sodium boron ratio meet above-mentioned requirements.The total salinity of concentrated solution, gross activity are sampled analyzing, and the heater RE shell-side variations in temperature of vaporizer is tracked.
PH value if the heater RE shell-side temperature of vaporizer is more than 137 DEG C, then needs vaporizer is carried out after adjusting.
(4) step (2), (3), are repeated until evaporation terminates.
Embodiment 2, the following is the present invention be applied to ridge Australia one phase nuclear power station waste liquid evaporation.
1, in ridge Australia one phase nuclear power station waste liquid evaporation element (L9TEU), November 9 days, occur that efficiency is low.In the processing procedure using conventional method, the on-the-spot condenser CS of discovery has a large amount of foam to produce when sampling, therefore suspect that efficiency is low excessive relevant with the foam of waste liquid in vaporizer EV, the investigation of relevant evaporation activity has found since to 2007 simultaneously, after every secondary evaporator EV adds the Na/B that alkali adjusts vaporizer EV concentrated solution, the efficiency of vaporizer EV all there will be this general character phenomenon of super inner quality standard, and the concentrated solution pH value of the vaporizer EV of ridge Australia one phase nuclear power station is 8.5, higher than Daya Bay nuclear power plant 6.3, confirm that vaporizer EV concentrated solution bubbles by overtesting serious.Use defoamer also the efficiency of vaporizer EV cannot be processed the inner quality standard 0.5MBq/m meeting power station3Within.Therefore, three wastes group of power plant determines first to start with from the pH adjusting concentrated solution, and it adjusts bottom line and is no more than the pH value 6.3 of Daya Bay nuclear power plant, to attempt whether can improving the efficiency of vaporizer EV.
November 24, after completing first time acid adding (we use the industrial nitric acid that concentration is 55% that power station is conventional).Vaporizer EV concentrated solution pH value is fallen below 7.0 by 8.4, and in acid adding process, the sampling result of condenser CS progressively be have decreased to less than 0.2MBq/m by initial 1.05MBq/m33, less than inner quality standard 0.5MBq/m3.Reach expection requirement.
After completing concentrated solution passback on November 27, the γ level of condenser CS becomes big, and the pH value of condenser CS raises, consistent with expection；PH value in vaporizer EV is basically unchanged, and radioactivity is also less much than originally, bigger with original expection difference, it is believed that be the reason that deposits to residue of the radioactive substance in former vaporizer EV.
November 29, determine again to turn down concentrated solution pH value, in order to control risk, first the pH value of vaporizer EV concentrated solution be adjusted to 6.8 by 7.0.
December 1-2 day, complete acid adding, it is contemplated that acid adding amount be 50L, reality has about added 42L.The pH value of final evaporation device EV concentrated solution be have decreased to 6.34 by 7.04.The sampling result of condenser CS is by the γ=5.4MBq/m before acid adding3, have decreased to less than 0.2MBq/m3, the γ=50257MBq/m of vaporizer EV concentrated solution3, than (γ=7343MBq/m before acid adding3) be significantly increased, it is believed that it is caused by intrasystem radioactive substance is acid washed.
December 5 days, the sampling result of vaporizer EV finds that the γ of concentrated solution has declined to a great extent 4264
MBq/m3, December has had dropped down to 1566MBq/m when within 6th, again sampling3.December 10th is 888MBq/m3, and concentrated solution color substantially shoals, from before brownish black become khaki, insoluble matter significantly reduces, and suspects that the possible cause that radioactivity reduces is radioactive substance such as silver etc. and other impurity (calcium, magnesium, silicon, phosphate, Organic substance etc.) there is the phenomenons such as precipitation, absorption together.Have confirmed that boron is not engaged in deposition process.
December 7 days, owing to current Na/B ratio is less than chemical specification requirement, determines progressively the NA/B ratio of L9TEU001 vaporizer EV to be transferred to normal (0.2-0.25).Adjust gross activity and the efficiency of following the tracks of L9TEU001 vaporizer EV during NA/B.
December completed to add alkali work, the sampling result of vaporizer EV: the radioactivity of concentrated solution has gone back up to 3963MBq/m at 12 morning3.Na/B=0.217, has reached expection.The state 5 sampling result still γ < 0.2MBq/m of condenser CS3, the detersive efficiency of vaporizer EV is there are no degradating trend.
Till December 14 to 19 days, the overstandard waste water of L9TEU03/04/016BA is all disposed (about 110m3), the equal γ < 0.2MBq/m of sampling result3.The L9TEU001 vaporizer EV gross activity of 19 days is 27981MBq/m3Significantly go up, concentrated solution color is also more obvious than last time to be deepened, sample has a little precipitation, contact agent dose rate in conjunction with Radiation monitoring point declines (being dropped to 2.6mSv/h by 5.8 time maximum) and the 9TEU-RE thermal efficiency rises, and (104MT be have decreased to 106 degree by 117 degree) judges, L9TEU001 vaporizer EV deposit exists reversible case.
Adjusting in concentrated solution pH value process, the radioactive variation situation of condenser CS distillate is as shown in Figure 2.
Three, the different pH laboratory simulation test on concentrated solution deposition impact:
Process of the test and result are shown in table 2 below:
Concentrated solution is affected process of the test and result by the different pH of table 2
Conclusion: result of the test with on-site actual situations coincide relatively good.By the change of pH, deposition presents reversible phenomenon.
Evaporation equipment is as it is shown in figure 1, Fig. 1 is evaporation element structure and flow chart thereof.Fig. 1 showing, the capital equipment of the liquid waste treatment system evaporation element installed in nuclear auxiliary building is as follows:
One heater (001RE), it ensures the supply of the auxiliary steam flow of heating concentrated solution.
One evaporation pillar (001EV), the release of overheated concentrated solution occurs in this device.This device ensure that the first time Gravity Separation between the steam of generation and the concentrated solution of incidental impurities.The main purpose of the atomizing spray of charging waste liquid is eliminate the steam that causes of concentrated solution overheated.By the embedding of the dropping liquid of formation and diluting effect, it also contributes to remove radioactive pollution.
One purification (removing alpha-contamination) pillar (001ZE), the steam from evaporation pillar is received within the lower at pillar.Alpha-contamination it is removed by what following means ensured:
By the flushing (backflow) of steam when running through 3 pallets coming that a part for condenser slips out that the circulation that thing and steam intersects carries out, normal reflux ratio is confirmed as 20%.
The metallic sieve passing through the mixing that the porosity successively decreased by 3 layer thicknesses is formed carries out finally except mist.
One reflux condenser (001CS), it is by the cooling water circulated at tube exterior, it is ensured that carry out the condensation of the steam being cleaned of auto purification (removing pollution) pillar.
One forced circulation pump (006PO), it is a centrifugal pump of horizontal axis.Its feature is: low-head, big flow.Its use is to ensure that evaporation pillar, heater and returns to the circulation of concentrated solution between evaporation pillar；Wash away pipeloop simultaneously, concentrated solution is had certain heat effect, to avoid evaporation circuit boron crystallization.
Claims (11)
1. a nuclear power station radioactive liquid waste evaporation process method, it is characterised in that comprise the following steps:
(1), first the various not reusable radioactive liquid waste that nuclear power station is formed is collected in corresponding preposition waste liquid tank；
(2), by the waste liquid in preposition waste liquid tank being delivered to vaporizer to be evaporated processing, the steam of evaporation is delivered to condenser condensation and is formed distillate, and being retained in vaporizer is concentrated solution, and distillate and concentrated solution carry out discharge detection；
(3), when the radioactivity of detection distillate is lower than hot drain standard 0.5MBq/m3Time discharge distillate；Being discharged by concentrated solution when detection concentrated solution reaches solidification standard and solidify, evaporation terminates；
When the radioactivity of detection distillate is equal to or higher than hot drain standard 0.5MBq/m3, and when boron concentration is less than 10000ppm in detection concentrated solution, carry out step (4)；
(4), in concentrated solution acid adding, the pH value of concentrated solution is progressively turned down to pH value be 5～7, then to equal to or higher than 0.5MBq/m3Distillate add-back concentrated solution in, repeat step (2), (3) until concentrated solution reaches solidification standard, evaporation terminates.
2. the nuclear power station radioactive liquid waste evaporation process method stated according to claim 1, it is characterised in that in step (3), the amount of described acid adding is by adopting chemical titration to determine concentrated solution.
3. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterised in that in step (3), adopts approximatioss acid adding step by step to reduce the pH value of concentrated solution.
4. nuclear power station radioactive liquid waste evaporation process method according to claim 3, it is characterised in that described approximatioss step by step is: waste liquid carrying out gradation acid adding gradation evaporation and regulates the pH value of concentrated solution, each acid addition time is for before evaporation starts every time；After often completing an acid adding evaporation, whether the radioactivity of sampling checking distillate has the trend gradually reduced, and verifies the whether consistent with the testing result of chemistry titration of concentrated solution pH value.
5. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterized in that, in step (3), during acid adding, concentrated solution is sampled detection analyze, sodium boron ratio in detection concentrated solution, Boron contents, total salinity, described solidification standard is that boron concentration reaches 40000-50000ppm, and in concentrated solution sodium boron ratio (weight ratio) for 0.20-0.25 time concentrated solution is solidified；Or total salinity reach 300g/L after concentrated solution is solidified.
6. nuclear power station radioactive liquid waste evaporation process method according to claim 5, it is characterized in that, in step (3), when the sodium boron ratio in testing result should not between 0.20-0.25 time, concentrated solution hydro-oxidation sodium is adjusted, makes sodium boron ratio meet above-mentioned requirements.
7. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterized in that, in described step (3), during acid adding, also need to be sampled the gross activity of concentrated solution analyzing, and the heater shell-side variations in temperature of vaporizer is tracked.
8. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterised in that in described step (3), institute's acid adding is nitric acid.
9. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterised in that in described step (2), distillate radiological measuring frequency is sampling detection before the discharge of each distillate.
10. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterised in that in described step (3), the sampling detection frequency of concentrated solution detects for sampling after often completing an acid adding operation.
11. nuclear power station radioactive liquid waste evaporation process method according to claim 1, it is characterised in that in described step (3), pH value if the heater RE shell-side temperature of vaporizer is more than 137 DEG C, then needs vaporizer is carried out after adjusting.
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| 低中水平放射性废液的水泥固化研究;谷万成;《湿法冶金》;20050331;第24卷(第1期);全文 * |
| 放射性废水处理技术概述;苗俊婷;《Science & Technology Information》;20111231(第23期);正文右侧第2段 * |
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