CN111489844A - Radioactive waste oil treatment system and radioactive waste oil treatment method - Google Patents

Radioactive waste oil treatment system and radioactive waste oil treatment method Download PDF

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Publication number
CN111489844A
CN111489844A CN201910079806.7A CN201910079806A CN111489844A CN 111489844 A CN111489844 A CN 111489844A CN 201910079806 A CN201910079806 A CN 201910079806A CN 111489844 A CN111489844 A CN 111489844A
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CN
China
Prior art keywords
circulation loop
waste oil
radioactive
radioactive waste
valve
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Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
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CN201910079806.7A
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Chinese (zh)
Inventor
马若霞
杨彬
刘强
伍灵
杨洋
荆黎
何琳璐
秦福初
方祥洪
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Chongqing Technology Branch Spic Yuanda Environmental Protection Engineering Co ltd
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Chongqing Technology Branch Spic Yuanda Environmental Protection Engineering Co ltd
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Application filed by Chongqing Technology Branch Spic Yuanda Environmental Protection Engineering Co ltd filed Critical Chongqing Technology Branch Spic Yuanda Environmental Protection Engineering Co ltd
Priority to CN201910079806.7A priority Critical patent/CN111489844A/en
Publication of CN111489844A publication Critical patent/CN111489844A/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/10Processing by flocculation
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/008Apparatus specially adapted for mixing or disposing radioactively contamined material
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing

Abstract

The embodiment of the invention provides a radioactive waste oil treatment system and a radioactive waste oil treatment method, wherein the system comprises a first circulation loop, a second circulation loop and a mixing tank for connecting the first circulation loop and the second circulation loop, and the mixing tank is provided with an oxygen inlet and a catalytic agent inlet; the first circulation loop is provided with a radioactive waste oil inlet, a degassing device and a first valve; a centrifugal machine and a second valve are arranged on the second circulation loop; wherein, only one valve of the first valve and the second valve is opened in the same time, when the first valve is opened, the first circulation loop is communicated with the mixing tank, and the second circulation loop is closed; when the second valve is opened, the second circulation loop is communicated with the mixing tank, and the first circulation loop is closed. The embodiment of the invention can remove radioactive substances in the radioactive waste oil.

Description

Radioactive waste oil treatment system and radioactive waste oil treatment method
Technical Field
The invention relates to the technical field of nuclear industry, in particular to a radioactive waste oil treatment system and a radioactive waste oil treatment method.
Background
With the development of nuclear power generation, nuclear technology application industries and the like, a certain amount of radioactive waste oil is generated in the processes of operation, maintenance, decommissioning and the like of nuclear setting. The kind of radioactive waste oil includes high viscosity lubricating oil such as vacuum pump oil, engine oil, rail oil, etc. The radioactive waste oil contains radioactive substances and thus cannot be discharged at will.
For example: the use of lubricating and hydraulic oils in reactor systems as a drive for mechanical systems may result in radioactive contamination of the lubricating and hydraulic oils during operation, thereby forming radioactive waste oils. Taking the example of a deuterium-uranium (CANDU) reactor in canada, the reactor produces about several hundred litres of radioactive waste oil per year. Due to the special properties of the radioactive waste oil, the difficulty of decontamination treatment is high, and the radioactive waste oil is difficult to treat by using a common purification treatment means (such as stabilizing treatment by adopting a common solidification (fixation) method) aiming at the radioactive waste oil (water). Moreover, the final waste solidified bodies of radioactive waste oils are not good in stability and containment of radionuclides (high leachability).
In the related art, radioactive waste oil is temporarily stored in an associated storage facility. In case of daily and monthly accumulations, the total amount of radioactive waste oil stored is gradually large, thereby increasing the cost of storage and reducing the safety during storage.
Therefore, the method for treating radioactive waste oil in the related art has the problem of low safety performance.
Disclosure of Invention
The embodiment of the invention provides a radioactive waste oil treatment system and a radioactive waste oil treatment method, and aims to solve the problem of low safety performance of a radioactive waste oil treatment method in the related art.
In order to solve the technical problems, the invention adopts the following technical scheme:
in a first aspect, an embodiment of the present invention provides a radioactive waste oil treatment system, including:
the device comprises a first circulation loop, a second circulation loop and a mixing tank connected with the first circulation loop and the second circulation loop, wherein the mixing tank is provided with an oxygen inlet and a catalytic agent inlet;
the first circulation loop is provided with a radioactive waste oil inlet, a degassing device and a first valve;
a centrifugal machine and a second valve are arranged on the second circulation loop;
wherein only one of the first valve and the second valve is open at a time, the first circulation loop is in communication with the mixing tank and the second circulation loop is closed when the first valve is open; when the second valve is opened, the second circulation loop is communicated with the mixing tank, and the first circulation loop is closed.
Optionally, a first filter is further disposed on the second circulation loop, and the first filter is disposed at an upstream end of the centrifuge along the second circulation loop.
Optionally, a cooler is further disposed on the second circulation loop, and the cooler is disposed between the centrifuge and the first filter.
Optionally, a heater is further disposed on the first circulation loop, and the heater is disposed at an upstream end of the mixing tank along the first circulation loop.
Optionally, a stirrer is arranged in the mixing tank.
Optionally, the centrifuge further comprises a waste oil outlet arranged on the second circulation loop, and the waste oil outlet is arranged at the downstream end of the centrifuge along the second circulation loop.
Optionally, the system further includes a first collection tank, the first collection tank is connected to the waste oil outlet through a first branch, and a third valve is arranged on the first branch.
Optionally, the radioactive waste oil treatment system further comprises a second collection tank connected to the centrifuge for collecting the radioactive solid particles centrifuged by the centrifuge from the radioactive waste oil.
Optionally, a sampling port is further disposed on the second circulation loop, and the sampling port is disposed at a downstream end of the centrifuge along the second circulation loop.
Optionally, the degasser comprises a degasser, a gas discharge pipeline connected to the gas outlet side of the degasser, and a second filter arranged on the gas discharge pipeline, wherein the second filter is used for filtering radioactive substances in the air discharged by the degasser.
Optionally, the radioactive waste oil inlet is connected to the first circulation loop through a second branch, and a third filter is arranged on the second branch and used for filtering solid impurities in the radioactive waste oil.
Optionally, a check valve is further disposed on the first circulation loop, and the check valve is disposed at a downstream end of the mixing tank along the first circulation loop.
In a second aspect, an embodiment of the present invention further provides a radioactive waste oil treatment method, which is applied to the radioactive waste oil treatment system described above, and the method includes:
closing the second circulation loop and communicating the first circulation loop;
transferring radioactive waste oil into the mixing tank;
introducing oxygen and a catalytic agent into the mixing tank so that the radioactive waste oil reacts with the oxygen and the catalytic agent to generate oil-insoluble radioactive solid particles;
closing the first circulation loop and communicating the second circulation loop;
opening a centrifuge to separate the radioactive solid particles from the radioactive waste oil.
In the embodiment of the invention, the radioactive waste oil is ensured to be chemically reacted with oxygen and catalytic agents through the first circulation loop and the mixing tank, radioactive substances in the radioactive waste oil are converted into radioactive solid particles, and then the radioactive solid particles are centrifuged out through the second circulation loop, so that the effect of removing the radioactive substances in the radioactive waste oil is achieved.
Drawings
In order to more clearly illustrate the technical solutions of the embodiments of the present invention, the drawings needed to be used in the description of the embodiments or the prior art will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art that other drawings can be obtained according to these drawings without creative efforts.
FIG. 1 is a block diagram of a radioactive waste oil treatment system according to an embodiment of the present invention;
FIG. 2 is a flow chart of a radioactive waste oil treatment method according to an embodiment of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are some, not all, embodiments of the present invention. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
Referring to fig. 1, which is a structural diagram of a radioactive waste oil treatment system according to an embodiment of the present invention, as shown in fig. 1, the radioactive waste oil treatment system includes:
the device comprises a first circulation loop 1, a second circulation loop 2 and a mixing tank 3 for connecting the first circulation loop 1 and the second circulation loop 2, wherein the mixing tank 3 is provided with an oxygen inlet 31 and a catalytic agent inlet 32;
the first circulation loop 1 is provided with a radioactive waste oil inlet 11, a degassing device 12 and a first valve 13;
the second circulation circuit 2 is provided with a centrifuge 21 and a second valve 22;
wherein, only one valve of the first valve 13 and the second valve 22 is opened at the same time, when the first valve 13 is opened, the first circulation loop 1 is communicated with the mixing tank 3, and the second circulation loop 2 is closed; when the second valve 22 is opened, the second circulation circuit 2 communicates with the mixing tank 3, and the first circulation circuit 1 is closed.
In the process of treating the radioactive waste oil, firstly introducing the radioactive waste oil to be treated into the first circulation loop 1 through the radioactive waste oil inlet 11, wherein the radioactive waste oil flows into the mixing tank 3 through the first circulation loop 1, and introducing oxygen and a catalytic agent respectively through the oxygen inlet 31 and the catalytic agent inlet 32, wherein the oxygen and the catalytic agent can perform chemical reaction with radioactive substances in the radioactive waste oil so as to convert the radioactive substances into radioactive solid particles which are insoluble in oil.
After the first circulation circuit 1 has been circulated one or more times, the second valve 22 is opened and the first valve 13 is closed, so that the first circulation circuit is closed and the used oil containing the radioactive solid particles is circulated only between the second circulation circuit 2 and the mixing tank 3. So as to separate the radioactive solid particles from the waste oil by the centrifuge 21 on the second circulation loop 2, thereby facilitating the recovery or purification and reuse of the waste oil obtained after the system treatment according to the common waste oil treatment mode.
Therein, the catalytic agent added to the mixing tank 3 is used to convert the radioactive substances in the radioactive waste oil into oil-insoluble radioactive solid particles for separation in the centrifuge 21. For example: in the case of radioactive waste oils containing tritium, strontium, cesium, cobalt and other nuclides, oxygen and metal catalysts may be used, such as: copper catalyst, iron catalyst to reduce the radioactivity of tritium, strontium, cesium, cobalt and other nuclides to form radioactive solid particles which are convenient to separate. It should be noted that. The kind and amount of the catalyst may vary according to the kind of radioactive substance, the amount of radioactive waste oil to be treated, the temperature of radioactive waste oil, and the like, and are not particularly limited herein.
In addition, the number of cycles of the first circulation circuit 1 may vary depending on the type of radioactive substance, the amount of radioactive waste oil to be treated, the temperature of the radioactive waste oil, etc., and it is only necessary to ensure that the radioactive substance in the radioactive waste oil is sufficiently reacted and reaches a certain conversion rate.
In addition, when the waste oil obtained after the treatment in the second circulation loop 2 still contains large radioactive substances, the second valve 22 can be closed and the first valve 13 can be opened, and a certain amount of oxygen and catalytic agent can be introduced into the mixing tank 3 to perform chemical reaction with the radioactive substances in the radioactive waste oil again. After the first circulation loop 1 circulates for a certain number of times, the first valve 13 is closed, the second valve 22 is opened, so that the radioactive waste oil enters the second circulation loop 2 to be subjected to radioactive solid particle separation, and the radioactive waste oil is circulated until the radioactive waste oil reaches the standard.
Optionally, in order to facilitate the sampling and testing of the waste oil in the second circulation loop 2, a sampling port 23 is further provided on the second circulation loop 2, and the sampling port 23 is provided at the downstream end of the centrifuge 21 along the second circulation loop 2.
Like this, alright with sampling port at any time to the waste oil that obtains after centrifuge handles to in detection.
Of course, the sampling port may be provided in the mixing tank, etc., and is not particularly limited herein.
In addition, the degassing device 12 is used to extract gases in the first circulation circuit 1, such as: the gas contained in the radioactive waste oil to be treated, the oxygen introduced into the mixing tank 3, the gas generated after the chemical reaction with the catalytic agent, and the like. The radioactive substances in the gas can be specifically removed, for example: the gas is mixed with gas particles of radioactive or toxic substances such as iodine (I), xenon (Xe) and the like.
As an alternative embodiment, as shown in fig. 1, degassing device 12 comprises: a degasser 121, a gas discharge pipe 122 connected to the gas outlet side of the degasser 121, and a second filter 123 provided on the gas discharge pipe 122, the second filter 123 being for filtering radioactive materials in the air discharged from the degasser 121.
The degasser 121 is used for extracting the gas in the first circulation loop 1, filtering the radioactive substances in the gas through the gas discharge pipe 122 and the second filter 123, and discharging the filtered gas to the atmosphere.
In addition, a gas exhaust line 122 may be provided with a gas pump 124 for providing power and direction to the gas in the gas exhaust line 122.
Therefore, the radioactivity of the gas discharged into the atmosphere can be reduced, and the radioactive substances of the gas are prevented from harming the environment and the life safety.
Optionally, a first filter 24 is further disposed on the second circulation circuit 2, and the first filter 24 is disposed at an upstream end of the centrifuge 21 along the second circulation circuit 2.
The first filter 24 is any one of a screen filter and an adsorption filter, and is used for filtering radioactive substances in the waste oil that have been converted into radioactive solid particles, and specifically, can filter radioactive solid particles with larger particle diameters.
Of course, it can also be used for filtering other solid impurities in the used oil, and is not particularly limited herein.
In this way, the filtration pressure of the centrifuge can be reduced by the preliminary filtration of the first filter.
Optionally, a cooler 25 is further disposed on the second circulation circuit 2, and the cooler 25 is disposed between the centrifuge 21 and the first filter 24.
Wherein, cooler 25 can reduce the temperature of waste oil to the temperature that matches with centrifuge 21, be convenient for separate it from the waste oil in centrifuge 21, can also avoid the waste oil of high temperature to damage centrifuge 21.
In addition, the oil temperature after the waste oil is cooled by the cooler 25 may be determined according to the requirement of the centrifuge 21, the temperature characteristic of the radioactive solid particles, and the like, and is not particularly limited herein.
Therefore, the temperature of the radioactive solid particles can be reduced, the radioactive solid particles can be more easily centrifuged from the waste oil, the treatment difficulty of the centrifuge is reduced, and the eccentricity is improved.
Optionally, a heater 14 is further disposed on the first circulation loop 1, and the heater 14 is disposed at an upstream end of the mixing tank 3 along the first circulation loop 1.
The heater 14 may be any type of heater such as an in-line heater, a heat exchanger, etc. for heating the used radioactive oil in the first circulation loop 1 to catalyze the reaction rate of the used radioactive oil mixed with oxygen and the catalytic agent.
The temperature of the oil obtained by heating may be 120 to 180 ℃, and of course, the temperature may be determined according to the kind of the catalyst, the number of cycles of the first circulation circuit, and the like, and is not particularly limited herein.
Therefore, the reaction speed of the radioactive waste oil, oxygen and the catalytic agent can be increased by heating the radioactive waste oil, so that the cycle times of the first circulation loop, the dosage of the catalytic agent and the like can be reduced, and the operation cost of the radioactive waste oil treatment system provided by the embodiment of the invention is reduced.
Optionally, a stirrer (not shown) is provided in the mixing tank 3.
Wherein, the stirrer can uniformly mix the radioactive waste oil in the mixing tank 3 with oxygen and catalytic agent, so as to avoid the problem of incomplete conversion of radioactive substances caused by non-uniform mixing.
Optionally, the radioactive waste oil treatment system further comprises: a waste oil outlet (not numbered) provided on the second circulation circuit 2, the waste oil outlet being provided at a downstream end of the centrifuge 21 along the second circulation circuit 2.
Wherein, this waste oil export is used for the radioactive waste oil processing system of waste oil discharge after will handling the completion to in order to carry out subsequent processing such as retrieving, purification to it.
In addition, the waste oil outlet may be disposed at other positions such as the mixing tank 3, and is not particularly limited herein.
Further, the radioactive waste oil treatment system further comprises: and a first collecting tank 4, wherein the first collecting tank 4 is connected to the waste oil outlet through a first branch 26, and a third valve 261 is arranged on the first branch 26.
Wherein the first collection tank 4 is used to collect the waste oil discharged from the waste oil outlet so as to collect the waste oil. The waste oil outlet in this embodiment can be regarded as the intersection of the first branch 26 and the second circulation circuit 2 as shown in fig. 2.
In addition, a sixth valve 29 is further provided at the waste oil outlet along the downstream end of the second circulation circuit 2, and in the case where the third valve 261 is opened, the sixth valve 29 is closed so that the waste oil in the second circulation circuit 2 is discharged through the waste oil outlet.
Optionally, the radioactive waste oil treatment system further comprises: a second collection tank 211 connected to the centrifuge 21 for collecting the radioactive solid particles centrifuged by the centrifuge 21 from the radioactive waste oil.
Therefore, the radioactive solid particles centrifuged from the radioactive waste oil by the centrifuge can be prevented from being retained in the centrifuge, so that the centrifuge is blocked or the difficulty of the centrifugation process is increased.
Optionally, the radioactive waste oil inlet 11 is connected to the first circulation circuit 1 through a second branch 15, and a third filter 151 is disposed on the second branch 15, and the third filter 151 is used for filtering solid impurities in the radioactive waste oil.
The third filter 151 may be a strainer filter for filtering solid impurities with large particle diameters contained in the used radioactive oil to be treated, thereby preventing the solid impurities from clogging pipes and devices in the used radioactive oil treatment system.
Optionally, a check valve 16 is further disposed on the first circulation circuit 1, and the check valve 16 is disposed at a downstream end of the mixing tank 3 along the first circulation circuit 1.
In this way, it is possible to avoid that the first circulation loop circulates in the opposite direction and causes a process error.
It is of course also possible to arrange the mixing tank 3 at a higher level, making use of the difference in topography to allow the oil to be treated to enter the degassing device 12 for treatment, avoiding its reverse circulation.
In addition, a first circulation pump 17 may be provided in the first circulation circuit 1 to supply power for circulation of the radioactive waste oil in the first circulation circuit 1 and guide the radioactive waste oil.
Similarly, a second circulation pump 27 may also be provided in the second circulation circuit 2 to provide power for circulation and direction of the radioactive waste oil in the second circulation circuit 2.
As shown in fig. 1, in the present embodiment, a first circulation pump is provided between the heater 14 and the deaerator 121, and a second circulation pump 27 is provided between the first filter 24 and the cooler 25.
In addition, a fourth valve 18 is provided in the first circulation circuit 1, and is provided at a downstream end of the mixing tank 3 along the first circulation circuit 1. The fourth valve 18 can be opened simultaneously with the first valve 13 and closed simultaneously to control the communication and closing of the first circulation circuit 1 together.
Furthermore, a fifth valve 28 is provided in the second circulation circuit 2, which is provided at the downstream end of the mixing tank 3 along the second circulation circuit 2. The five valves 28 can be opened simultaneously with the second valve 22 and closed simultaneously to control the communication and closing of the second circulation circuit 2 in common.
It should be noted that, in this embodiment, the operation steps of opening and closing each valve, adding oxygen and a catalytic agent, adjusting the power of each device, and the like may be automatically controlled by a control system, so that the radioactive waste oil treatment system provided in the embodiment of the present invention can be operated fully automatically.
Of course, the above-mentioned operation steps may also be implemented by a manual control mode, and are not limited in detail herein.
In addition, the radioactive waste oil treatment system can be fixedly installed in production environments of nuclear power plants, nuclear industry workshops and the like so as to treat radioactive waste oil generated in the nuclear power plants or the nuclear industry production processes.
Of course, the radioactive waste oil treatment system can be made as a mobile device, and the radioactive waste oil is introduced into the system from the radioactive waste oil inlet 11 of the system only when the radioactive waste oil treatment is needed.
In the embodiment of the invention, the radioactive waste oil is ensured to be chemically reacted with oxygen and catalytic agents through the first circulation loop and the mixing tank, radioactive substances in the radioactive waste oil are converted into radioactive solid particles, and then the radioactive solid particles are centrifuged through the second circulation loop.
Referring to fig. 2, a flow chart of a radioactive waste oil treatment method according to an embodiment of the present invention is shown, the method can be applied to the radioactive waste oil treatment system provided in the embodiment shown in fig. 1, and as shown in fig. 2, the method includes the following steps:
and step 201, closing the second circulation loop and communicating the first circulation loop.
Specifically, the manner of closing the second circulation loop and communicating the first circulation loop may refer to the control process of closing the second circulation loop and communicating the first circulation loop in the previous embodiment, which is not described herein again.
Step 202, transferring radioactive waste oil into the mixing tank.
In order to transport the radioactive waste oil into the mixing tank, the first circulation pump on the first circulation loop may be turned on to provide power for the radioactive waste oil and guide the radioactive waste oil.
In addition, the radioactive waste oil is continuously circulated in the first circulation circuit after being transferred into the mixing tank.
And 203, introducing oxygen and a catalytic agent into the mixing tank to enable the radioactive waste oil to react with the oxygen and the catalytic agent to generate oil-insoluble radioactive solid particles.
The process of introducing the oxygen and the catalytic agent can last for a long time, and the introduced oxygen and the catalytic agent are continuously circulated in the first circulation loop along with the radioactive waste oil, so that the residual oxygen, gas and the like contained in the radioactive waste oil are discharged out of the first circulation loop through a degassing device in the first circulation loop.
And step 204, closing the first circulation loop and communicating the second circulation loop.
The specific execution process in this step may refer to the previous embodiment, and is not described herein again.
Step 205, turning on a centrifuge to separate the radioactive solid particles from the radioactive waste oil.
The radioactive waste oil treatment method provided by the embodiment of the invention can obtain the same beneficial effects as the system shown in the figure 1, and is not repeated herein for avoiding repetition.
In addition, in the embodiment of the method, after the first circulation loop is communicated, a heater on the first circulation loop can be started, so that the reaction speed of the radioactive waste oil with the oxygen and the catalytic agent is accelerated after the temperature of the radioactive waste oil is raised.
In this embodiment, the first filter and the cooler on the second circulation loop may be further opened to filter the solid particles with larger diameter through the first filter before the centrifugal machine is used to separate the radioactive solid particles, and the temperature of the waste oil is reduced through the cooler to further improve the centrifugal efficiency of the centrifugal machine.
Optionally, after turning on the centrifuge, the method further comprises:
detecting the radioactivity of the waste oil obtained after the treatment of the centrifugal machine;
when the radioactivity is larger than a preset value, the first circulation loop is communicated, and the second circulation loop is closed;
introducing oxygen and the catalytic agent into the mixing tank;
closing the first circulation loop and communicating the second circulation loop;
opening a centrifuge to separate the radioactive solid particles from the radioactive waste oil.
Wherein a waste oil sample can be extracted from a sampling port on the second circulation loop to perform the step of detecting the radioactivity of the waste oil obtained after the centrifuge processing.
In addition, when the radioactivity is larger than the preset value, the radioactive waste oil obtained after the centrifugal treatment still exceeds the standard, therefore, the waste oil is introduced into the first circulation loop and the mixing tank to further react with oxygen and the catalytic agent, and after the second reaction is finished, the radioactive solid particles are separated through the second circulation loop.
It should be noted that the preset value may be set according to the requirements of subsequent processing, and is not specifically limited herein.
In addition, the process is a process which can be repeated for many times, and the process can be repeatedly executed only under the condition that the radioactivity of the waste oil obtained after the treatment of the second circulation loop is detected to be more than the preset value.
Therefore, the radioactivity of the waste oil obtained after the radioactive waste oil treatment method is less than a preset value can be ensured, and the precision and the reliability of the treatment method are further improved.
In addition, the number of cycles of the first and second circulation loops can be greatly increased, for example: the first circulation loop is circulated for 20 times, and the second circulation loop is circulated for 10 times, so as to ensure that the radioactive substances can be sufficiently converted into radioactive solid particles and be sufficiently separated.
Of course, after the radioactive waste oil is treated, the radioactive waste oil can be discharged through the waste oil outlet or collected through the first collection tank, which is not limited in particular.
The above description is only for the specific embodiments of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art can easily conceive of the changes or substitutions within the technical scope of the present invention, and the changes or substitutions should be covered within the scope of the present invention. Therefore, the protection scope of the present invention shall be subject to the protection scope of the claims.

Claims (13)

1. A radioactive spent oil treatment system, comprising:
the device comprises a first circulation loop, a second circulation loop and a mixing tank connected with the first circulation loop and the second circulation loop, wherein the mixing tank is provided with an oxygen inlet and a catalytic agent inlet;
the first circulation loop is provided with a radioactive waste oil inlet, a degassing device and a first valve;
a centrifugal machine and a second valve are arranged on the second circulation loop;
wherein only one of the first valve and the second valve is open at a time, the first circulation loop is in communication with the mixing tank and the second circulation loop is closed when the first valve is open; when the second valve is opened, the second circulation loop is communicated with the mixing tank, and the first circulation loop is closed.
2. The system of claim 1, further comprising a first filter disposed on the second recirculation loop, the first filter disposed at an upstream end of the centrifuge along the second recirculation loop.
3. The system of claim 2, further comprising a cooler disposed on the second recirculation loop, the cooler disposed between the centrifuge and the first filter.
4. The system of claim 1, further comprising a heater disposed on the first circulation loop, the heater being disposed at an upstream end of the mixing tank along the first circulation loop.
5. The system of claim 1, wherein an agitator is disposed within the mixing tank.
6. The system of claim 1, further comprising:
and a waste oil outlet arranged on the second circulation loop, wherein the waste oil outlet is arranged at the downstream end of the centrifuge along the second circulation loop.
7. The system of claim 6, further comprising:
the first collecting tank is connected to the waste oil outlet through a first branch, and a third valve is arranged on the first branch.
8. The system of claim 7, further comprising:
a second collection tank connected to the centrifuge for collecting radioactive solid particles centrifuged by the centrifuge from the radioactive waste oil.
9. The system of claim 1, wherein the second circulation loop is further provided with a sampling port disposed at a downstream end of the centrifuge along the second circulation loop.
10. The system of claim 1, wherein the degasser comprises a degasser, a gas discharge line connected to a gas outlet side of the degasser, and a second filter disposed on the gas discharge line for filtering radioactive materials from air discharged by the degasser.
11. The system according to claim 1, characterized in that said radioactive waste oil inlet is connected to said first circulation circuit through a second branch, and on said second branch a third filter is provided for filtering solid impurities in said radioactive waste oil.
12. The system of claim 1, further comprising a check valve disposed on the first circulation loop, the check valve disposed at a downstream end of the mixing tank along the first circulation loop.
13. A radioactive waste oil treatment method applied to the radioactive waste oil treatment system according to any one of claims 1 to 12, wherein the method comprises:
closing the second circulation loop and communicating the first circulation loop;
transferring radioactive waste oil into the mixing tank;
introducing oxygen and a catalytic agent into the mixing tank so that the radioactive waste oil reacts with the oxygen and the catalytic agent to generate oil-insoluble radioactive solid particles;
closing the first circulation loop and communicating the second circulation loop;
opening a centrifuge to separate the radioactive solid particles from the radioactive waste oil.
CN201910079806.7A 2019-01-28 2019-01-28 Radioactive waste oil treatment system and radioactive waste oil treatment method Pending CN111489844A (en)

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CN201910079806.7A CN111489844A (en) 2019-01-28 2019-01-28 Radioactive waste oil treatment system and radioactive waste oil treatment method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201910079806.7A CN111489844A (en) 2019-01-28 2019-01-28 Radioactive waste oil treatment system and radioactive waste oil treatment method

Publications (1)

Publication Number Publication Date
CN111489844A true CN111489844A (en) 2020-08-04

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Application Number Title Priority Date Filing Date
CN201910079806.7A Pending CN111489844A (en) 2019-01-28 2019-01-28 Radioactive waste oil treatment system and radioactive waste oil treatment method

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