CN109754888A - A method of radioactivity waste oil is handled using spent sorbents in nuclear power station - Google Patents
A method of radioactivity waste oil is handled using spent sorbents in nuclear power station Download PDFInfo
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- CN109754888A CN109754888A CN201910040044.XA CN201910040044A CN109754888A CN 109754888 A CN109754888 A CN 109754888A CN 201910040044 A CN201910040044 A CN 201910040044A CN 109754888 A CN109754888 A CN 109754888A
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- waste oil
- spent sorbents
- power station
- nuclear power
- radioactivity waste
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Abstract
The present invention provide it is a kind of using in nuclear power station spent sorbents processing radioactivity waste oil method, this method include the following steps are included: (1) recycling nuclear power station in spent sorbents, the spent sorbents are placed in contactor;(2) radioactivity waste oil is added into contactor by preset ratio;(3) after standing preset time, the radioactivity waste oil for eliminating radionuclide is discharged from contactor.Using the present invention provides the method radioactivity waste oil that can not only make that treated to reach solution control horizontal, release the supervision to it, management cost can be reduced can reach " treatment of wastes with processes of wastes against one another " by reducing managing risk.
Description
Technical field
The invention belongs to Radwastes treatment disposal technology fields, and in particular to a kind of to utilize spent sorbents in nuclear power station
The method for handling radioactivity waste oil.
Background technique
With the development of the social economy, the demand for electric power resource is increasing, nuclear power is as a kind of efficient, clean
The energy has been increasingly concerned by people.But while bringing huge economic interests, nuclear power station operational process
The processing problem of the radioactive waste of middle generation is also got worse.
The radioactivity waste oil that nuclear power station operation generates belongs to a kind of more special radioactive waste.Radioactivity waste oil mainly wraps
Include highly viscous lubricating oil, such as pumping fluid, machine oil, rail oil;And low-flash fuel oil, as gasoline, TBP/ kerosene,
Diesel oil etc..Radioactivity waste oil is usually a kind of low and intermediate level radioac, containing a small amount of β/gamma activity nucleic, they be by with put
Penetrating property substance contacts and is contaminated or by volatility radionuclide contamination, also contains a small amount of work generated by neutron irradiation
Change product.Although radioactivity waste oil annual output is little, fails to be dealt carefully with, dispose, be temporarily stored into dispersed placement mostly
In waste storage facility.
The problem of radioactivity waste oil has special physicochemical characteristics and therefore brings;Its good fluidity and containing tritium,
The radionuclides such as strontium, caesium, cobalt may cause radioactive pollution diffusion;It contains volatility and low-flash combustible component, and stores
Radiolysis can generate certain flammable radiolysis gas during depositing, and there are the risks of burning;Its partial organic substances has chemical toxicity,
Being in contact with it for a long time will affect health.And run after a certain period of time in nuclear facilities, radioactivity waste oil cumulant is increasingly
Greatly, security risk is formd, great puzzlement is caused to waste management;If by natural calamities such as earthquake, tsunamis, or it is terrified
Serious harm easily is brought to the public and environment when attack, in some instances it may even be possible to cause social unrest.Therefore, it is necessary to develop one kind
The method that radioactivity waste oil can be effectively handled.
On the other hand, nuclear power station operation needs to use a large amount of adsorbent, to handle radioactive liquid waste, exhaust gas etc.;These
Adsorbent is mainly ion exchange resin, molecular sieve etc., is just needed to change after the replacement demand that it reaches setting, replacement amount pole
Greatly, wherein steam generator blowdown system generates radioactive waste ion exchange resin and heavy water reactor removes the radioactivity that tritium system generates
The radioactive contamination level of deposed molecular sieve is extremely low, is typically in the threshold level of low-level waste, it might even be possible to it is horizontal to reach solution control.
Tritium system is removed due to steam generator blowdown system and heavy water reactor to want the performance indicator of above-mentioned ion exchange resin and molecular sieve
Ask higher, causing it, there are also certain adsorption capacities in replacement.
Absorption is that pollutant is adsorbed on to one of adsorbent hole technique, after organic pollutant is contacted with adsorbent,
It is eventually converted into solid matter.There are many type of absorbent, poly- from very simple material (such as wood sawdust) to complicated alkane
Object is closed, but conventional adsorbent not only has the problems such as adsorption effect is poor, and efficiency is relatively low, and in Radwastes treatment
Non- substance of putting largely is introduced no matter from Radioactive waste management security standpoint, or from economy point is obviously all improper
's.
Using the nucleic in the light contamination radioactivity material Adsorption of Radioactive waste oil for still having the ability centainly adsorbed, reach
It is effectively treated, it is horizontal that the radionuclide in treated radioactivity waste oil reaches solution control, can release the supervision to it, not only
" treatment of wastes with processes of wastes against one another " can also be reached by reducing managing risk, reduce management cost.
Therefore, it is necessary to develop one kind can effectively handle radioactivity waste oil, application value with higher, and can be effective
The environmental problem for avoiding being likely to occur and social concern method.
Summary of the invention
In view of the deficiencies in the prior art, it is utilized in nuclear power station at spent sorbents the object of the present invention is to provide a kind of
The method for managing radioactivity waste oil can be realized to the maximum extent when can safely, quickly guarantee that radioactivity waste oil reaches solution control level
Waste minimizes theory.
To achieve the above objectives, the technical solution adopted by the present invention is that: it is a kind of to be put using spent sorbents processing in nuclear power station
The method of penetrating property waste oil, the described method comprises the following steps:
(1) spent sorbents in nuclear power station are recycled, the spent sorbents are placed in contactor;
(2) radioactivity waste oil is added into contactor by preset ratio;
(3) after standing preset time, the radioactivity waste oil for eliminating radionuclide is discharged from contactor.
Further, the spent sorbents level of activity recycled in step (1) meets GB 27742-2011 to solution control material
Nucleic limit value.
Further, the spent sorbents be steam generator blowdown system generate radioactive waste ion exchange resin or
Heavy water reactor removes the Spent Radioactive molecular sieve that tritium system generates.
Further, the spent sorbents that recycling is placed in contactor in step (1) are without free water.
Further, in step (1), the spent sorbents are placed in contactor as natural packing.
Further, in step (2), the radioactivity waste oil is recycled using dynamical fashion and iterates through spent sorbents.
Further, in step (3), the radioactivity waste oil for eliminating radionuclide is discharged specifically from contactor
Are as follows:
Go out by the oil discharge outlet discharge being arranged on contactor or with pumping.
Further, in step (3), preset time is 5~7 days.
Further, after step (3) further include:
Judge whether the spent sorbents in contactor reach exchange capacity, is replaced if reaching.
Effect of the invention is that being had the advantage that using method of the present invention
1. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station provided by the invention, mainly utilizes core
Nucleic in the material Adsorption of Radioactive waste oil for the light contamination that power station operation generates achievees the effect that purification radioactivity waste oil,
To realize being effectively treated for radioactivity waste oil, waste oil can reach non-zoom level after processing, its risk is down to close to zero wind
Dangerous rank.
2. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station provided by the invention, treatment process
Simply, the level of activity of treated waste oil is lower than the radioactive waste limit value of nuclear power station, can be used as it is non-put waste processing, or press
It is managed according to cleaning solution control, reduces intermediate link, effectively reduce the risk of escape of radioactivity.
3. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station provided by the invention, using nuclear power station
The light contamination material adsorption treatment radioactivity waste oil generated is run, that is, radioactivity waste oil has been effectively treated, and is utilized slight
Contaminated material is truly realized " treatment of wastes with processes of wastes against one another ", has practiced the theory of waste minimum.
Detailed description of the invention
Fig. 1 is the flow diagram of one embodiment of the method for the invention.
Specific embodiment
To keep the technical problems solved, the adopted technical scheme and the technical effect achieved by the invention clearer, below
It will the technical scheme of the embodiment of the invention will be described in further detail in conjunction with attached drawing.Obviously, described embodiment is only
It is a part of the embodiment of the present invention, instead of all the embodiments.Based on the embodiments of the present invention, ordinary skill people
Member's every other embodiment obtained without making creative work, belongs to the scope of protection of the invention.
As shown in Figure 1, Fig. 1 is the flow diagram of one embodiment of the method for the invention.The method includes following steps
It is rapid:
Step 101: the spent sorbents are placed in contactor by spent sorbents in recycling nuclear power station.
Pumping or other mode of movement can be used by spent sorbents from temporary container transport to contactor.It requires emphasis
It is that although the spent sorbents recycled from nuclear power station have light contamination, but its level of activity meets GB 27742-2011 to solution
Control the nucleic limit value of material.
In a specific embodiment, the spent sorbents are the Spent Radioactive ion that steam generator blowdown system generates
Exchanger resin.
In other embodiments, the Spent Radioactive molecule that the spent sorbents can also generate for heavy water reactor detritiation system
Sieve.
It may also be noted that the spent sorbents that recycling is placed in contactor are free of free water, and it is placed in absorption
It is natural packing when in container.
Step 102: radioactivity waste oil being added into contactor by preset ratio.
Preset ratio is a value range, amount, the Spent Radioactive of specific value and radioactivity waste oil to be processed
The original level of activity of oil and treated that processing that radioactivity waste oil need to reach is horizontal related.In the present embodiment, it gives up and adsorbs
The mass ratio of agent and radioactivity waste oil is 1:2~4.It should also be noted that, the density of general machine oil is 0.95g/ml or so, examine
Considering its density such as the impurity in used oil is about 1g/ml, is measured to the used oil of liquid with milliliter in ordinary test, to solid
An adsorbent gram metering, therefore what is limited herein is mass ratio.
Pumping can be used, radioactivity waste oil is delivered to contactor, needs to consider the protection to pump in transmission process, that is, exist
Strainer is installed before pump additional with the biggish impurity of filtration fraction particle, the general strainer for using 100 μ.It needs to guarantee to adsorb during standing
Container is in normal temperature and pressure state, and is closed using entity in order to avoid causing unnecessary influence to Spent Radioactive oil processing.
Dynamical fashion, which can be used, makes radioactivity waste oil be repeatedly cycled through spent sorbents, and the specific time needs according to the actual situation
It considers.
Step 103: after standing preset time, the radioactivity waste oil of radionuclide will be eliminated from contactor
Discharge.
The preset time of standing is 5~7 days.
After every batch of radioactivity waste oil reaches preset time, contactor and sampling and measuring are opened, if meeting nucleic removal
It is required that then the waste oil for eliminating radionuclide is discharged from contactor or with being pumped out;If nucleic removal effect is unsatisfactory for
Related request then needs to change adsorbent material and re-starts absorption, until reaching design requirement.
Also need to judge whether the spent sorbents in contactor reach exchange capacity when handling radioactivity waste oil, if reaching
Then replace.
Illustrate beneficial effect brought by the present invention below with 3 specific embodiments.
Embodiment 1:
Ion exchange resin type GR-2-0NG (H), radioactivity waste oil 300ml, resin 150g, the standing adsorption time 5 days.
Initial activity nucleic level of activity in radioactivity waste oil:137Cs 1.68Bq/g,60Co 3.51Bq/g;It is useless after adsorption treatment
Radionuclide specific activity in oil is horizontal:137Cs 0.017Bq/g,60Co 0.180Bq/g;For137The decontamination factor of Cs is
98.71,60The decontamination factor of Co is 19.42, it is contemplated that treated, and total γ is 0.084Bq/g, meets what nuclear power station was generally arranged
The radioactive waste of 0.1Bq/g and the non-limit value requirement for putting waste can be used as non-waste of putting and handle.
Example 2:
Ion exchange resin type GR-2-0NG (H), radioactivity waste oil 200ml, resin 10g, the standing adsorption time 5 days.
Initial activity nucleic level of activity in radioactivity waste oil:137Cs 10.87Bq/g,60Co 11.27Bq/g;After adsorption treatment
Radionuclide specific activity in waste oil is horizontal:137Cs 0.69Bq/g,60Co 2.81Bq/g;For137The decontamination factor of Cs is
15.62,60The decontamination factor of Co is 4.00;It is expected that after processing137The level of activity of Cs is lower than nucleic as defined in GB 27742-2011
Limit value meets solution control condition, after processing60The level of activity of Co is higher than nucleic limit value as defined in GB 27742-2011, is unsatisfactory for solving
Control condition.
Example 3:
Molecular sieve model PNX-1, radioactivity waste oil 300ml, molecular sieve 90g, the standing adsorption time 5 days.Radioactivity waste oil
Middle initial activity nucleic level of activity:137Cs 1.68Bq/g,60Co 3.51Bq/g;The radiation in waste oil after adsorption treatment
Property nucleic level of activity:137Cs 1.42Bq/g,60Co 2.99Bq/g;For137The decontamination factor of Cs is 1.18,60The decontamination of Co
Coefficient is 1.17.
It is different from the prior art feature, it is provided by the invention a kind of to handle radioactivity waste oil using spent sorbents in nuclear power station
Method, using nuclear power station operation generate light contamination material adsorption treatment radioactivity waste oil, radioactivity has both been effectively treated
Waste oil, and light contamination material is utilized, it is truly realized " treatment of wastes with processes of wastes against one another ", has practiced the theory of waste minimum.
It will be understood by those skilled in the art that system of the present invention and system are not limited to institute in specific embodiment
The embodiment stated, specific descriptions above are intended merely to explain the purpose of the present invention, are not intended to limit the present invention.This field skill
Art personnel can derive other implementation manners according to the technical scheme of the present invention, and also belong to the scope of the technical innovation of the present invention, this
The protection scope of invention is defined by the claims and their equivalents.
Claims (9)
1. it is a kind of using in nuclear power station spent sorbents processing radioactivity waste oil method, which is characterized in that the method includes with
Lower step:
(1) spent sorbents in nuclear power station are recycled, the spent sorbents are placed in contactor;
(2) radioactivity waste oil is added into contactor by preset ratio;
(3) after standing preset time, the radioactivity waste oil for eliminating radionuclide is discharged from contactor.
2. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In,
The spent sorbents level of activity recycled in step (1) meets GB 27742-2011 to the nucleic limit value of solution control material.
3. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 2
In,
The spent sorbents are the radioactive waste ion exchange resin or heavy water reactor detritiation system that steam generator blowdown system generates
The Spent Radioactive molecular sieve that system generates.
4. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In,
The spent sorbents that recycling is placed in contactor in step (1) are without free water.
5. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In,
In step (1), the spent sorbents are placed in contactor as natural packing.
6. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In,
In step (2), the radioactivity waste oil is recycled using dynamical fashion and iterates through spent sorbents.
7. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In in step (3), the radioactivity waste oil for eliminating radionuclide is discharged from contactor specifically:
Go out by the oil discharge outlet discharge being arranged on contactor or with pumping.
8. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In,
In step (3), preset time is 5~7 days.
9. a kind of method using spent sorbents processing radioactivity waste oil in nuclear power station, feature exist according to claim 1
In after step (3) further include:
Judge whether the spent sorbents in contactor reach exchange capacity, is replaced if reaching.
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Cited By (4)
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CN112489830A (en) * | 2019-09-11 | 2021-03-12 | 中核核电运行管理有限公司 | Method for cleaning and controlling waste resin of blow-down system of steam generator of nuclear power plant |
CN112901140A (en) * | 2021-01-26 | 2021-06-04 | 四川松云科技有限公司 | Application of neutron activation method in oil field logging |
CN112924267A (en) * | 2019-12-06 | 2021-06-08 | 南京理工大学 | Method for detecting nuclide volatilization ratio in evaporation and concentration process of simulated high-level radioactive waste liquid |
CN113707354A (en) * | 2021-08-18 | 2021-11-26 | 中国人民解放军63653部队 | Comprises239Pu、90Sr and137electrochemical separation and fixation method for large-volume radioactive waste liquid of Cs |
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Cited By (7)
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CN112489830A (en) * | 2019-09-11 | 2021-03-12 | 中核核电运行管理有限公司 | Method for cleaning and controlling waste resin of blow-down system of steam generator of nuclear power plant |
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CN113707354A (en) * | 2021-08-18 | 2021-11-26 | 中国人民解放军63653部队 | Comprises239Pu、90Sr and137electrochemical separation and fixation method for large-volume radioactive waste liquid of Cs |
CN113707354B (en) * | 2021-08-18 | 2024-02-09 | 中国人民解放军63653部队 | Containing 239 Pu、 90 Sr and 137 electrochemical separation and fixation method for large-volume radioactive waste liquid of Cs |
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