CN109524143B - Method and system for treating radioactive waste liquid of nuclear power plant - Google Patents
Method and system for treating radioactive waste liquid of nuclear power plant Download PDFInfo
- Publication number
- CN109524143B CN109524143B CN201811390279.3A CN201811390279A CN109524143B CN 109524143 B CN109524143 B CN 109524143B CN 201811390279 A CN201811390279 A CN 201811390279A CN 109524143 B CN109524143 B CN 109524143B
- Authority
- CN
- China
- Prior art keywords
- waste liquid
- tritium
- low
- tds
- treatment
- Prior art date
- 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.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/20—Disposal of liquid waste
- G21F9/22—Disposal of liquid waste by storage in a tank or other container
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
Abstract
The invention discloses a method for treating radioactive waste liquid of a nuclear power plant, which comprises a waste liquid treatment and reuse method and comprises the following steps: dividing the radioactive waste liquid into high tritium waste liquid and low tritium waste liquid according to different tritium activity concentrations; dividing the low tritium waste liquid into low tritium low TDS waste liquid and low tritium high TDS waste liquid according to different TDS contents; treating the high tritium waste liquid, and monitoring the treated high tritium waste liquid to be discharged; treat low tritium low TDS waste liquid and low tritium high TDS waste liquid respectively, the low TDS waste liquid of low tritium after the processing and the monitoring of low tritium high TDS waste liquid treat multiplexing and/or the monitoring treats the emission. Correspondingly, the invention further provides a nuclear power plant radioactive waste liquid treatment system. The method can be used for treating radioactive waste liquid with different properties generated by the operation of the nuclear power plant in a targeted manner, and the water requirement of a nuclear island part of the nuclear power plant can be reduced.
Description
Technical Field
The invention belongs to the technical field of waste treatment of nuclear power plants, and particularly relates to a method and a device for treating radioactive waste liquid of a nuclear power plant.
Background
In order to meet the ever-increasing energy demand of economy and society, ensure the long-term stable supply of energy, reduce the influence of power generation on the environment, and actively promote nuclear power construction to be an important policy of the current energy construction in China. However, some radioactive wastes are inevitably generated in the process of generating electricity by using nuclear energy, and the treatment and minimization of the radioactive wastes are concerned by countries all over the world in order to protect human health and environmental safety. Meanwhile, to solve the increasingly severe energy problem, the related national departments are steadily advancing the planning and site selection work of inland nuclear power plants on the premise of ensuring safety and reliability. Compared with coastal nuclear power plants, inland nuclear power plants are prone to shortage of available water resources. By reasonably treating the radioactive waste liquid, the reuse of part of the waste liquid discharged after treatment can be realized, thereby reducing the water demand of a nuclear power plant to the maximum extent and effectively relieving the condition of water shortage in areas with water resource shortage.
However, the existing radioactive waste liquid treatment system rarely considers the reuse of radioactive waste liquid, and does not relate to the treatment of secondary waste generated after the radioactive waste liquid treatment. For example, the technical scheme disclosed in the chinese patent application "nuclear power plant radioactive liquid waste treatment system" (application No. 201310065960, published as 2013, 6 and 5) does not consider the reuse of radioactive liquid waste after treatment, nor the treatment of secondary waste generated after radioactive liquid waste treatment.
Disclosure of Invention
The technical problem to be solved by the present invention is to provide a method and a device for treating radioactive waste liquid in a nuclear power plant, which can treat radioactive waste liquid with different properties generated during operation of the nuclear power plant in a targeted manner and reduce the water demand of a nuclear island part of the nuclear power plant.
In order to solve the technical problems, the invention adopts the following technical scheme:
a nuclear power plant radioactive waste liquid treatment method comprises a waste liquid treatment and reuse method, wherein the waste liquid treatment and reuse method comprises the following steps:
dividing the radioactive waste liquid into high tritium waste liquid and low tritium waste liquid according to different tritium activity concentrations;
dividing the low tritium waste liquid into low tritium low TDS waste liquid and low tritium high TDS waste liquid according to different TDS contents;
treating the high tritium waste liquid, and monitoring the treated high tritium waste liquid to be discharged;
treat low tritium low TDS waste liquid and low tritium high TDS waste liquid respectively, the low TDS waste liquid of low tritium after the processing and the monitoring of low tritium high TDS waste liquid treat multiplexing and/or the monitoring treats the emission.
Further, the step of treating the high tritium waste liquid comprises the following steps:
s11, carrying out ultrafiltration process treatment on the high tritium waste liquid;
s12, carrying out ion exchange process treatment on the high tritium waste liquid obtained in the step S11;
the method for treating the low tritium and low TDS waste liquid comprises the following steps:
s21, carrying out ultrafiltration process treatment on the low tritium and low TDS waste liquid;
s22, carrying out ion exchange process treatment on the low tritium and low TDS waste liquid obtained in the step S21;
the method for treating the low-tritium high-TDS waste liquid comprises the following steps:
and S31, carrying out energy-saving evaporation process treatment on the high-tritium high-TDS waste liquid.
Further, before the high tritium waste liquid is treated, the high tritium waste liquid is divided into high tritium low TDS waste liquid and high tritium high TDS waste liquid according to different TDS contents in the high tritium waste liquid,
performing steps S11-S12 on the high tritium low TDS waste liquid;
and carrying out energy-saving evaporation process treatment on the high-tritium high-TDS waste liquid.
Further, the step of treating the high tritium waste liquid further comprises the following steps:
s13, performing ion exchange refining treatment on the high tritium low TDS waste liquid obtained in the step S12 and/or the high tritium high TDS waste liquid obtained after the treatment of the energy-saving evaporation process;
s14, carrying out boron removal and refining treatment on the high tritium low TDS waste liquid and/or the high tritium high TDS waste liquid obtained in the step S13;
the step of treating the low tritium and low TDS waste liquid further comprises:
s23, performing ion exchange refining treatment on the low tritium and low TDS waste liquid obtained in the step S22;
s24, carrying out boron removal and refining treatment on the low tritium and low TDS waste liquid obtained in the step S23;
the step of treating the low tritium high TDS waste liquid further comprises:
s33, performing ion exchange refining treatment on the low tritium high TDS waste liquid obtained in the step S32;
and S34, performing boron removal and refining treatment on the low tritium high TDS waste liquid obtained in the step S33.
Further, the method for treating the radioactive waste liquid of the nuclear power plant also comprises a secondary waste treatment method, and the secondary waste treatment method comprises the following steps:
carrying out cement fixation process treatment on the waste membrane generated in the ultrafiltration process, and conveying the treated waste membrane to a waste storage for temporary storage;
carrying out polymer curing process treatment on waste resin generated in the ion exchange process, and conveying the treated waste resin to a waste storage for temporary storage;
and carrying out concentrated solution drying process treatment on the concentrated solution generated in the energy-saving evaporation process, and conveying the treated concentrated solution to a waste warehouse for temporary storage.
The invention also provides a radioactive waste liquid treatment system of a nuclear power plant, which comprises a high tritium waste liquid treatment system and a low tritium waste liquid treatment system,
the high tritium waste liquid treatment system comprises a high tritium waste liquid collecting tank, a first ultrafiltration process unit, a first ion exchange process unit and a high tritium waste liquid middle tank which are connected in sequence,
the high tritium waste liquid collecting tank is used for collecting high tritium waste liquid;
the first ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the high tritium waste liquid;
the first ion exchange process unit is used for carrying out ion exchange process treatment on the high tritium waste liquid;
collecting the high tritium waste liquid treated by the first ion exchange process unit in a high tritium waste liquid intermediate tank;
the low tritium waste liquid treatment system comprises a low tritium and low TDS waste liquid treatment subsystem, a low tritium and high TDS waste liquid treatment subsystem and a low tritium waste liquid intermediate tank,
the low tritium and low TDS waste liquid treatment subsystem comprises a low tritium and low TDS waste liquid collecting tank, a second ultrafiltration process unit and a second ion exchange process unit which are connected in sequence,
the low tritium and low TDS waste liquid collecting tank is used for collecting low tritium and low TDS waste liquid;
the second ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the low tritium and low TDS waste liquid;
the output end of the second ion exchange process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out ion exchange process treatment on the low tritium and low TDS waste liquid;
the low tritium high TDS waste liquid treatment subsystem comprises a low tritium high TDS waste liquid collecting tank and a second energy-saving evaporation process unit,
the low tritium high TDS waste liquid collecting tank is used for collecting low tritium high TDS waste liquid;
the input end of the second energy-saving evaporation process unit is connected with the low tritium high TDS waste liquid collecting tank, the output end of the second energy-saving evaporation process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out energy-saving evaporation process treatment on the low tritium high TDS waste liquid,
and collecting the low tritium and low TDS waste liquid treated by the second ion exchange process unit and the low tritium and high TDS waste liquid treated by the second energy-saving evaporation process unit in a low tritium waste liquid intermediate tank.
Further, the high tritium waste liquid collecting tank comprises a high tritium low TDS waste liquid collecting sub-tank for collecting the high tritium low TDS waste liquid and a high tritium high TDS waste liquid collecting sub-tank for collecting the high tritium high TDS waste liquid,
the input end of the first ultrafiltration process unit is connected with a high tritium and low TDS waste liquid collecting sub-tank in the high tritium waste liquid collecting tank,
the high tritium waste liquid treatment system also comprises a first energy-saving evaporation process unit, wherein the input end of the first energy-saving evaporation process unit is connected with the high tritium high TDS waste liquid collecting sub-tank, and the output end of the first energy-saving evaporation process unit is connected with the high tritium waste liquid middle tank and is used for carrying out energy-saving evaporation process treatment on the high tritium high TDS waste liquid.
Further, the high tritium waste liquid treatment system also comprises a first ion exchange fine treatment unit, a first boron removal fine treatment unit and an effluent discharge tank,
the input end of the first ion exchange fine treatment unit is connected with the high tritium waste liquid intermediate tank and is used for carrying out ion exchange fine treatment on the high tritium waste liquid;
the input end of the first boron-removing fine treatment unit is connected with the first ion exchange fine treatment unit and is used for carrying out boron-removing fine treatment on the high tritium waste liquid;
and the effluent discharge tank is connected with the output end of the first ion exchange fine treatment unit and the output end of the first boron removal fine treatment unit respectively and is used for collecting the high tritium waste liquid treated by the first ion exchange fine treatment unit and the high tritium waste liquid treated by the first boron removal fine treatment unit.
Further, the low tritium waste liquid treatment system also comprises a second ion exchange fine treatment unit, a second boron removal fine treatment unit and an effluent multiplexing tank,
the input end of the second ion exchange fine treatment unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out ion exchange fine treatment on the low tritium waste liquid;
the input end of the second boron-removing fine treatment unit is connected with the second ion exchange fine treatment unit and is used for carrying out boron-removing fine treatment on the low tritium waste liquid;
and the effluent multiplexing tank is connected with the output end of the second ion exchange fine treatment unit and the output end of the second boron removal fine treatment unit and is used for collecting the low tritium waste liquid treated by the second ion exchange fine treatment unit and the low tritium waste liquid treated by the second boron removal fine treatment unit.
Further, the radioactive waste liquid treatment system of the nuclear power plant also comprises a secondary waste treatment system, the secondary waste treatment system comprises a cement fixing process unit, a polymer curing process unit and a concentrated solution drying treatment unit,
the cement fixing process unit is respectively connected with the first ultrafiltration process unit and the second ultrafiltration process unit and is used for carrying out cement fixing process treatment on waste membranes generated in the first ultrafiltration process unit and the second ultrafiltration process unit;
the polymer curing process unit is respectively connected with the first ion exchange process unit and the second ion exchange process unit and is used for carrying out polymer curing process treatment on the waste resin generated in the first ion exchange process unit and the second ion exchange process unit;
and the concentrated solution drying treatment unit is respectively connected with the first energy-saving evaporation process unit and the second energy-saving evaporation process unit and is used for carrying out concentrated solution drying treatment on concentrated solutions generated in the first energy-saving evaporation process unit and the second energy-saving evaporation process unit.
Furthermore, the first ultrafiltration process unit is also connected with the first energy-saving evaporation process unit, and the first energy-saving evaporation process unit is also used for treating the concentrated solution generated in the first ultrafiltration process unit;
the second ultrafiltration process unit is also connected with the second energy-saving evaporation process unit, and the second energy-saving evaporation process unit is also used for treating the concentrated solution generated in the second ultrafiltration process unit.
Further, the output end of the low tritium and low TDS waste liquid collecting tank is respectively connected with the low tritium and high TDS waste liquid collecting tank and the high tritium waste liquid collecting tank,
the output end of the low tritium high TDS waste liquid collecting tank is also respectively connected with the high tritium waste liquid collecting tank and the second ultrafiltration process unit,
the output end of the low tritium waste liquid intermediate tank is also connected with an effluent discharge tank,
the output end of the effluent multiplexing tank is also connected with an effluent discharge tank.
The invention has the following beneficial effects:
according to the method, two independent sets of radioactive waste liquid treatment process flows are arranged according to different tritium activity concentrations in radioactive waste liquid generated in the operation of a nuclear power plant, so that the discharge of the waste liquid with higher tritium activity concentration in the nuclear power plant after treatment and the reuse of the waste liquid with lower tritium activity concentration or basically no tritium after treatment can be realized; moreover, different treatment processes are adopted to treat radioactive waste liquid with different properties generated by the operation of the nuclear power plant in a targeted manner, so that the generation amount of secondary waste is reduced while the treated radioactive waste liquid meets the emission requirement; meanwhile, different types of secondary wastes are treated by pertinently matching different types of treatment processes, so that the generation amount of solid wastes brought by the secondary wastes is reduced.
The method and the device can reduce the water demand of the nuclear island part of the nuclear power plant to the maximum extent, and effectively relieve the condition of water shortage of the nuclear power plant in areas lacking water resources; the method improves the minimum level of radioactive wastes of the nuclear power plant and reduces the influence of the operation of the nuclear power plant on the environment.
Drawings
Fig. 1 is a schematic flow chart of a method for treating radioactive waste liquid from a nuclear power plant in embodiment 1 of the present invention.
In the figure: 1-high tritium waste liquid collecting tank; 2-low tritium and low TDS waste liquid collecting tank; 3-low tritium high TDS waste liquid collecting tank; 4. 5-ultrafiltration process; 6. 7-ion exchange process; 8-a middle tank for high tritium waste liquid; 9-low tritium waste liquid intermediate tank; 10. 11-ion exchange fine treatment; 12-effluent discharge tank; 13-effluent reuse tank; 14. 15-energy-saving evaporation process; 16. 17-boron removal and fine treatment; 18-cement fixation process; 19-polymer curing process; 20-concentrated solution drying process.
In the figure, the solid line
Represents a waste liquid treatment line; dotted line
Represents a treatment line for secondary waste and solid waste;
Detailed Description
The technical solution of the present invention will be described clearly and completely with reference to the accompanying drawings, and it should be understood that the described embodiments are a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be obtained by a person skilled in the art without any inventive step based on the embodiments of the present invention, are within the scope of the present invention.
The invention provides a method for treating radioactive waste liquid of a nuclear power plant, which comprises a waste liquid treatment and reuse method, wherein the waste liquid treatment and reuse method comprises the following steps:
dividing the radioactive waste liquid into high tritium waste liquid and low tritium waste liquid according to different tritium activity concentrations;
dividing the low tritium waste liquid into low tritium low TDS waste liquid and low tritium high TDS waste liquid according to different TDS contents;
treating the high tritium waste liquid, and monitoring the treated high tritium waste liquid to be discharged;
treat low tritium low TDS waste liquid and low tritium high TDS waste liquid respectively, the low TDS waste liquid of low tritium after the processing and the monitoring of low tritium high TDS waste liquid treat multiplexing and/or the monitoring treats the emission.
Correspondingly, the invention also provides a radioactive waste liquid treatment system of the nuclear power plant, which comprises a high tritium waste liquid treatment system and a low tritium waste liquid treatment system,
the high tritium waste liquid treatment system comprises a high tritium waste liquid collecting tank, a first ultrafiltration process unit, a first ion exchange process unit and a high tritium waste liquid middle tank which are connected in sequence,
the high tritium waste liquid collecting tank is used for collecting high tritium waste liquid;
the first ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the high tritium waste liquid;
the first ion exchange process unit is used for carrying out ion exchange process treatment on the high tritium waste liquid;
collecting the high tritium waste liquid treated by the first ion exchange process unit in a high tritium waste liquid intermediate tank;
the low tritium waste liquid treatment system comprises a low tritium and low TDS waste liquid treatment subsystem, a low tritium and high TDS waste liquid treatment subsystem and a low tritium waste liquid intermediate tank,
the low tritium and low TDS waste liquid treatment subsystem comprises a low tritium and low TDS waste liquid collecting tank, a second ultrafiltration process unit and a second ion exchange process unit which are connected in sequence,
the low tritium and low TDS waste liquid collecting tank is used for collecting low tritium and low TDS waste liquid;
the second ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the low tritium and low TDS waste liquid;
the output end of the second ion exchange process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out ion exchange process treatment on the low tritium and low TDS waste liquid;
the low tritium high TDS waste liquid treatment subsystem comprises a low tritium high TDS waste liquid collecting tank and a second energy-saving evaporation process unit,
the low tritium high TDS waste liquid collecting tank is used for collecting low tritium high TDS waste liquid;
the input end of the second energy-saving evaporation process unit is connected with the low tritium high TDS waste liquid collecting tank, the output end of the second energy-saving evaporation process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out energy-saving evaporation process treatment on the low tritium high TDS waste liquid,
and collecting the low tritium and low TDS waste liquid treated by the second ion exchange process unit and the low tritium and high TDS waste liquid treated by the second energy-saving evaporation process unit in a low tritium waste liquid intermediate tank.
Example 1:
as shown in fig. 1, the embodiment discloses a method for treating radioactive waste liquid from a nuclear power plant, which includes a waste liquid treatment and reuse method, and the waste liquid treatment and reuse method includes the following steps:
step one, dividing radioactive waste liquid into high tritium waste liquid and low tritium waste liquid according to different tritium activity concentrations.
And classifying and collecting radioactive waste liquid generated by the operation of the nuclear power plant according to different tritium activity concentrations so as to divide the radioactive waste liquid into high tritium waste liquid and low tritium waste liquid. Specifically, for radioactive waste liquid, if the activity concentration of tritium therein is more than or equal to 1X 105Bq/L is set as high tritium waste liquid, and all the high tritium waste liquid is collected in a high tritium waste liquid collecting tank 1; if the activity concentration of tritium is less than 1 × 105Bq/L, isAnd determining as low tritium waste liquid.
And step two, dividing the low tritium waste liquid into low tritium high TDS waste liquid and low tritium low TDS waste liquid according to different TDS contents.
And further dividing the low tritium waste liquid into low tritium low TDS waste liquid and low tritium high TDS waste liquid according to different TDS (total dissolved solids) in the low tritium waste liquid. Specifically, for the low tritium waste liquid, if the TDS is more than or equal to 1000ppm (mg/L), the low tritium high TDS waste liquid is set, and all the low tritium high TDS waste liquid is collected in a low tritium high TDS waste liquid collecting tank 3; if the TDS is less than 1000ppm (mg/L), the waste liquid with low tritium and low TDS is set, and the waste liquid with low tritium and low TDS is collected in the waste liquid collecting tank 2.
Preferably, it can be further divided into high tritium high TDS liquid waste and high tritium low TDS liquid waste to high tritium waste liquid according to the difference of TDS concentration, and correspondingly, high tritium waste liquid collecting tank 1 includes two subslots, namely, a high tritium low TDS liquid waste collecting subslot (not shown in fig. 1) and a high tritium high TDS collecting subslot (not shown in fig. 1). Specifically, if TDS of the high tritium waste liquid is more than or equal to 1000ppm (mg/L), the high tritium waste liquid with high TDS is set and collected in a high tritium waste liquid with high TDS collector sub-tank; if the TDS is less than 1000ppm (mg/L), high tritium and low TDS waste liquid is set, and collected in a high tritium and low TDS waste liquid collecting sub-tank.
Of course, according to the operation experience of present nuclear power plant, because the TDS in the high tritium waste liquid of the vast majority is very low, consequently also can only set up high tritium waste liquid collecting vat 1, and no longer the subdivision is into two subslots, and whole high tritium waste liquid all collects in high tritium waste liquid collecting vat 1 promptly, to the processing of the high tritium waste liquid of collecting in high tritium waste liquid collecting vat 1 all according to follow-up high tritium low TDS waste liquid the process flow go on can.
And step three, treating the high tritium waste liquid, and monitoring the treated high tritium waste liquid to be discharged.
Specifically, the steps for treating the high tritium and low TDS waste liquid are as follows:
carrying out ultrafiltration process 4 treatment on the high tritium and low TDS waste liquid flowing out of the high tritium and low TDS waste liquid collecting sub-tank so as to effectively remove radioactive nuclides existing in a particulate matter state and a colloid state in the waste liquid; and then an ion exchange process 6 is carried out to remove nuclides existing in an ionic state in the waste liquid, and the treated high tritium and low TDS waste liquid is collected in a high tritium waste liquid intermediate tank 8 (a node N01 to a node N35).
The steps for treating the high tritium and high TDS waste liquid are as follows:
high tritium high TDS waste liquid that flows out in collecting the sub-groove to high tritium high TDS waste liquid carries out energy-conserving evaporation technology 14 and handles, and the high tritium high TDS waste liquid after the processing is collected in high tritium waste liquid intermediate tank 8 (node N05-N06).
In practice, the high tritium waste liquid (including the high tritium low TDS waste liquid treated by the ultrafiltration process 4 and the ion exchange process 6 and the high tritium high TDS waste liquid treated by the energy-saving evaporation process 14) collected in the high tritium waste liquid intermediate tank 8 is usually required to have a radionuclide concentration of not more than 1000Bq/L except tritium and carbon 14, so that the requirement of the national standard GB6249-2011 'nuclear power plant environmental radiation protection regulation' on coastal sites can be met.
Sampling the high tritium waste liquid in the high tritium waste liquid intermediate tank 8, and if the high tritium waste liquid meets the discharge standard, monitoring and then discharging (through a node N09); if the discharge standard is not met, the following treatment is carried out, namely, the high tritium waste liquid flowing out from the high tritium waste liquid intermediate tank 8 is subjected to ion exchange refining treatment 10, and the high tritium waste liquid after the ion exchange refining treatment 10 can be collected in the effluent discharge tank 12 (node N36 to node N02).
For a pressurized water reactor nuclear power plant, because the high tritium waste liquid may contain boron, the high tritium waste liquid after ion exchange refining treatment 10 is preferably subjected to boron removal refining treatment 16, and the treated waste liquid is finally collected in an effluent discharge tank 12 to be monitored and discharged (node N20 to node N21).
In practice, after being treated by the ion exchange fine treatment process 10, the high tritium waste liquid collected in the effluent discharge tank 12 is generally required to have a radionuclide concentration of not more than 100Bq/L except tritium and carbon 14, so as to meet the requirement of the national standard GB6249-2011 "radiation protection regulations for nuclear power plant environment" on inland sites.
And step four, respectively treating the low tritium low TDS waste liquid and the low tritium high TDS waste liquid, and monitoring the low tritium low TDS waste liquid and the low tritium high TDS waste liquid after treatment for reuse and/or for monitoring for discharge.
Specifically, the steps for treating the low tritium and low TDS waste liquid are as follows:
carrying out ultrafiltration process 5 treatment on the low tritium and low TDS waste liquid flowing out of the low tritium and low TDS waste liquid collecting tank 2 so as to effectively remove radioactive nuclides existing in a particulate matter state and a colloid state in the waste liquid; and then the ion exchange process 7 is carried out to remove the nuclide existing in an ionic state in the waste liquid, and the treated low-tritium and low-TDS waste liquid is collected in a low-tritium waste liquid intermediate tank 9 (a node N03 to a node N37).
The steps for treating the waste liquid with low tritium and high TDS are as follows:
the low tritium high TDS waste liquid that flows out among the low tritium high TDS waste liquid collecting vat 3 carries out energy-conserving evaporation technology 15 and handles, and the low tritium high TDS waste liquid after the processing is collected in low tritium waste liquid intermediate tank 9 (node N07 to node N08).
And sampling the low tritium waste liquid collected in the low tritium waste liquid intermediate tank 9, and if the low tritium waste liquid meets the multiplexing standard, multiplexing the low tritium waste liquid after further treatment (sequentially passing through nodes N17 and N10).
In practice, the low tritium waste liquid (including the low tritium low TDS waste liquid treated by the ultrafiltration process 5 and the ion exchange process 7 and the low tritium high TDS waste liquid treated by the energy-saving evaporation process 15) collected in the low tritium waste liquid intermediate tank 9 is usually required to have a radionuclide concentration of not more than 1000Bq/L except tritium and carbon 14, so that the requirement of the national standard GB6249-2011 'nuclear power plant environmental radiation protection regulation' on coastal sites can be met.
The low tritium waste liquid collected in the low tritium waste liquid intermediate tank 9 is sampled, and if the low tritium waste liquid does not meet the reuse standard, the following treatment is required, namely, the low tritium waste liquid flowing out from the low tritium waste liquid intermediate tank 8 is subjected to ion exchange refining treatment 11, and the low tritium waste liquid after the ion exchange refining treatment 11 is collected in an outflow reuse tank 13 (node N38 to node N04).
For a pressurized water reactor nuclear power plant, because the low tritium waste liquid may contain boron, the low tritium waste liquid after the ion exchange polishing 11 is preferably sent to a second boron removal polishing unit for boron removal polishing 17 (node N22 to node N23), and the treated low tritium waste liquid is finally collected in an effluent reuse tank 13 for further treatment and reuse.
In practice, after being treated by the ion exchange fine treatment process 11, the low tritium waste liquid collected in the effluent reuse tank 13 is required to have a radionuclide concentration of not more than 100Bq/L except tritium and carbon 14, so as to meet the requirement of the national standard GB6249-2011 environmental radiation protection regulations of nuclear power plants on inland sites.
It should be noted that, when the above step three and step four are performed, there is no time order limitation, and both steps may be performed simultaneously or may be performed sequentially.
Preferably, the low tritium waste liquid intermediate tank 9 and the effluent reusing tank 13 can be respectively connected with the effluent discharge tank 12 through pipelines (node N17 to node N19, node N18, and node N18 to node N19), so that when the nuclear power plant temporarily does not need to reuse the waste liquid and the treated low tritium waste liquid in the low tritium waste liquid intermediate tank 9 and the effluent reusing tank 13 can meet the discharge standard, the low tritium waste liquid in the low tritium waste liquid intermediate tank 9 and the effluent reusing tank 13 can be discharged into the effluent discharge tank 12 to monitor the discharge to be completed.
The ultrafiltration process, the ion exchange process, the energy-saving evaporation process, the ion exchange polishing and the boron removal polishing in the embodiment can be realized by adopting the existing technical means.
After the radioactive waste liquid of the nuclear power plant is treated, partial secondary waste can be remained. Therefore, the method for treating the radioactive waste liquid of the nuclear power plant in the embodiment is preferable, and a method for treating secondary waste is also included.
As shown in fig. 1, in this embodiment, the secondary waste treatment method includes the steps of:
carrying out cement fixation process treatment on the waste membranes generated by the ultrafiltration process 4 in the step S11 and the ultrafiltration process 5 in the step S21, fixing the waste membranes in a steel barrel through cement to form a stable steel barrel waste package, and temporarily storing the treated waste membranes in a waste warehouse (node N24 to node N26; node N25 to node N26);
carrying out polymer curing process treatment on the waste resin generated by the ion exchange process 6 in the step S12 and the ion exchange process 7 in the step S22, wherein the polymer curing process is carried out at normal temperature, and epoxy resin-based curing agent and coagulant are mixed and then mixed with the waste resin or radioactive salt to complete curing, so that the method has the advantages of simple operation, high containment rate, good waste leaching resistance and the like, and the treated waste resin is sent to a waste storage for temporary storage (node N32 to node N34; node N33 to node N34);
concentrated solution drying treatment is carried out on concentrated solution generated in the energy-saving evaporation processes 14 and 15, the concentrated solution after treatment is dried in a steel barrel, then the concentrated solution is transported to a waste warehouse and is placed into a concrete High Integrity Container (HIC) for temporary storage, and then the concentrated solution is transported to the waste warehouse for temporary storage (node N28 to node N29; node N31 to node N29).
Therefore, the method in the embodiment can be used for processing the secondary wastes of different types in a targeted manner by matching with different types of processing technologies, and can effectively reduce the secondary wastes and the solid wastes brought by processing the secondary wastes.
Preferably, the low tritium and low TDS waste liquid collecting tank 2 and the low tritium and high TDS waste liquid collecting tank 3 can be respectively connected with the high tritium waste liquid collecting tank 1 through one-way pipelines (node N11 to node N12; node N13 to node N14), that is, only the low tritium waste liquid is allowed to be discharged to the high tritium waste liquid, and tritium pollution caused by the fact that the high tritium waste liquid enters the low tritium waste liquid is avoided.
The low tritium and low TDS waste liquid collecting tank 2 is connected with the low tritium and high TDS waste liquid collecting tank 3 through a one-way pipeline, if through sampling monitoring, when TDS in low tritium and low TDS waste liquid in the low tritium and low TDS waste liquid collecting tank 2 is found to be high, the low tritium and high TDS waste liquid collecting tank 3 can be discharged, and is collected in a low tritium and waste liquid intermediate tank 9 (from a node N15 to a node N08 through a node N07) after being processed through an energy-saving evaporation process 15; when the TDS in the low tritium waste liquid of discovery low tritium high TDS waste liquid collecting vat 3 is lower, can export it to the second ultrafiltration process unit in, handle the back through ultrafiltration process 5 and ion exchange process 7 and collect in low tritium waste liquid intermediate tank 9 (node N16 to node N37), it is less that the low tritium high TDS waste liquid volume that produces when considering nuclear power plant operation is less, and low tritium low TDS waste liquid volume is great, thereby can utilize low tritium high TDS waste liquid collecting vat 3 as far as possible, reduce the utilization of low tritium low TDS waste liquid collecting vat 2, ensure to have sufficient collection volume to low tritium low TDS waste liquid.
Therefore, the method in the implementation has the advantages that two independent sets of radioactive waste liquid treatment processes are arranged according to different tritium concentrations in waste liquid generated in the operation of the nuclear power plant, and the functions of discharge after treatment of the waste liquid with high tritium concentration in the nuclear power plant and reuse after treatment of the waste liquid with low tritium concentration or without tritium basically can be realized. Meanwhile, different treatment processes are adopted to treat radioactive waste liquid with different properties generated in the operation of the nuclear power plant in a targeted manner, so that the generation amount of secondary waste can be reduced while the treated radioactive waste liquid meets the emission requirement.
Example 2:
the embodiment provides a nuclear power plant's radioactive liquid waste processing system, and it includes high tritium liquid waste processing system and low tritium liquid waste processing system.
As shown in fig. 1, the high tritium waste liquid treatment system includes a high tritium waste liquid collection tank 1, a first ultrafiltration process unit, a first ion exchange process unit, and a high tritium waste liquid intermediate tank 8, which are connected in sequence. The high tritium waste liquid collecting tank 1 is used for collecting high tritium waste liquid; the first ultrafiltration process unit is used for carrying out ultrafiltration process 4 treatment on the high tritium waste liquid; the first ion exchange process unit is used for carrying out ion exchange process 6 treatment on the high tritium waste liquid; and collecting the high tritium waste liquid treated by the first ion exchange process unit in a high tritium waste liquid intermediate tank 8.
Preferably, the high tritium waste liquid collecting tank 1 comprises a high tritium low TDS waste liquid collecting sub-tank for collecting high tritium low TDS waste liquid and a high tritium high TDS waste liquid collecting sub-tank for collecting high tritium high TDS waste liquid,
the input end of the first ultrafiltration process unit is specifically connected with a high tritium and low TDS waste liquid collecting sub-tank in a high tritium waste liquid collecting tank,
preferably, the high tritium waste liquid treatment system also comprises a first energy-saving evaporation process unit, the input end of the first energy-saving evaporation process unit is connected with the high tritium high TDS waste liquid collecting sub-tank, and the output end of the first energy-saving evaporation process unit is connected with the high tritium waste liquid middle tank 8 and is used for carrying out 14 treatment on the high tritium high TDS waste liquid through an energy-saving evaporation process.
Further, the high tritium waste liquid treatment system also comprises a first ion exchange fine treatment unit, a first boron removal fine treatment unit and an effluent discharge tank 12.
The input end of the first ion exchange fine treatment unit is connected with the high tritium waste liquid intermediate tank 8 and is used for carrying out ion exchange fine treatment 10 on the high tritium waste liquid;
the input end of the first boron removal fine treatment unit is connected with the first ion exchange fine treatment unit and is used for carrying out boron removal fine treatment on the high tritium waste liquid 16;
and the effluent discharge tank 12 is connected with the output end of the first ion exchange fine treatment unit and the output end of the first boron removal fine treatment unit respectively and is used for collecting the high tritium waste liquid treated by the first ion exchange fine treatment unit and the high tritium waste liquid treated by the first boron removal fine treatment unit.
The high tritium waste liquid generated by the operation of a nuclear power plant is completely collected in a high tritium waste liquid collecting tank 1, according to the operation experience of the nuclear power plant, the TDS (total dissolved solids) of most of the high tritium waste liquid is very low, so that most of the high tritium waste liquid (namely the high tritium low TDS waste liquid) enters a high tritium low TDS waste liquid collecting sub-tank, the high tritium waste liquid firstly enters a first ultrafiltration process unit and is treated by an ultrafiltration process 4, the ultrafiltration process 4 can effectively remove radionuclides existing in particulate matters and colloid states in the high tritium waste liquid, then the high tritium waste liquid enters a first ion exchange process unit and is treated by an ion exchange process 6 to remove nuclides existing in ion states in the high tritium waste liquid, and the treated high tritium waste liquid is collected in a high tritium waste liquid intermediate tank 8 (node N01 to node N35); for a small part of high tritium waste liquid (high tritium and high TDS waste liquid) collected in the high tritium and high TDS waste liquid collecting sub-tank, the small part of high tritium waste liquid is firstly put into a first energy-saving evaporation process unit to be treated by an energy-saving evaporation process 14, and then the small part of high tritium waste liquid is collected in a high tritium waste liquid intermediate tank 8 (nodes N05 to N06); the treated waste liquid collected in the high tritium waste liquid intermediate tank 8 is subjected to sampling, direct monitoring and discharge (through a node N09) meeting the discharge standard are realized, the waste liquid which does not meet the discharge standard can enter a first ion exchange process unit to be reprocessed through ion exchange polishing 10, the treated liquid effluent is collected in an effluent discharge tank 12 to be monitored and discharged (a node N36-a node N02), for a pressurized water reactor nuclear power plant, the high tritium waste liquid may contain boron, therefore, the high tritium waste liquid after the ion exchange polishing 10 can also enter a first boron removal polishing unit to be subjected to boron removal polishing 16 (a node N20-a node N21), and the high tritium waste liquid after boron removal enters the effluent discharge tank 12.
The low tritium waste liquid treatment system comprises a low tritium and low TDS waste liquid treatment subsystem, a low tritium and high TDS waste liquid treatment subsystem and a low tritium waste liquid intermediate tank 9.
The low tritium and low TDS waste liquid treatment subsystem comprises a low tritium and low TDS waste liquid collecting tank 2, a second ultrafiltration process unit and a second ion exchange process unit which are sequentially connected. Wherein, the low tritium and low TDS waste liquid collecting tank 2 is used for collecting low tritium and low TDS waste liquid; the second ultrafiltration process unit is used for carrying out ultrafiltration process 5 treatment on the low tritium and low TDS waste liquid; and the output end of the second ion exchange process unit is connected with the low tritium waste liquid intermediate tank 9 and is used for carrying out the treatment of the ion exchange process 7 on the low tritium and low TDS waste liquid.
The low-tritium high-TDS waste liquid treatment subsystem comprises a low-tritium high-TDS waste liquid collecting tank 3 and a second energy-saving evaporation process unit. A low tritium high TDS waste liquid collecting tank 3 for collecting low tritium high TDS waste liquid; the input end of the second energy-saving evaporation process unit is connected with the low tritium high TDS waste liquid collecting tank 3, and the output end of the second energy-saving evaporation process unit is connected with the low tritium waste liquid intermediate tank 9 and is used for carrying out energy-saving evaporation process 15 treatment on the low tritium high TDS waste liquid; the low tritium and low TDS waste liquid treated by the second ion exchange process unit and the low tritium and high TDS waste liquid treated by the second energy-saving evaporation process unit are collected in a low tritium waste liquid intermediate tank 9.
Preferably, the low tritium waste liquid treatment system further comprises a second ion exchange fine treatment unit, a second boron removal fine treatment unit and an effluent reusing tank 13. The input end of the second ion exchange fine treatment unit is connected with the low tritium waste liquid intermediate tank 9 and is used for carrying out ion exchange fine treatment 11 on the low tritium waste liquid; the input end of the second boron removal fine treatment unit is connected with the second ion exchange fine treatment unit and is used for carrying out boron removal fine treatment 17 on the low tritium waste liquid; and the effluent multiplexing tank 13 is connected with the output end of the second ion exchange fine treatment unit and the output end of the second boron removal fine treatment unit and is used for collecting the low tritium waste liquid treated by the second ion exchange fine treatment unit and the low tritium waste liquid treated by the second boron removal fine treatment unit.
Low tritium low TDS waste liquid and low tritium high TDS waste liquid of nuclear power plant are respectively collected in a low tritium low TDS waste liquid collecting tank 2 and a low tritium high TDS waste liquid collecting tank 3, the low tritium low TDS waste liquid firstly enters a second ultrafiltration process unit and is treated by an ultrafiltration process 5, the ultrafiltration process 5 can effectively remove radionuclides existing in particulate matters and colloid states in the low tritium waste liquid and then enters a second ion exchange process unit and is treated by an ion exchange process 7, nuclides existing in ion states in the low tritium waste liquid are removed, and the treated low tritium low TDS waste liquid is collected in a low tritium waste liquid intermediate tank 9 (node N03 to node N37); the low tritium high TDS waste liquid firstly enters a second energy-saving evaporation process unit and is treated by an energy-saving evaporation process 14, and the treated low tritium high TDS waste liquid is collected in a low tritium waste liquid intermediate tank 9 (from a node N07 to a node N08); the treated waste liquid collected in the low tritium waste liquid intermediate tank 9 is sampled, the treated waste liquid meeting the multiplexing standard is directly reused after being further treated (sequentially passes through nodes N17 and N10), the waste liquid which does not meet the multiplexing standard enters a second ion exchange fine treatment unit and is reprocessed through ion exchange fine treatment 11, and the treated liquid effluent is collected in an effluent multiplexing tank 12 to be monitored and discharged (nodes N38 to N04); for a pressurized water reactor nuclear power plant, because the low tritium waste liquid may contain boron, the low tritium waste liquid after ion exchange polishing 11 can also enter a first boron removal polishing unit for boron removal polishing 17 (node N22 to node N23), and the low tritium waste liquid after boron removal enters an effluent reuse tank 13.
In this embodiment, in order to treat the secondary waste, it is preferable that the nuclear power plant radioactive waste liquid treatment system further includes a secondary waste treatment system including a cement fixing process unit, a polymer curing process unit, and a concentrated liquid drying process unit. Wherein the content of the first and second substances,
a cement fixing process unit which is respectively connected with the first ultrafiltration process unit and the second ultrafiltration process unit and is used for carrying out cement fixing process 18 treatment (through a node N24 and a node N25) on the waste membranes generated in the first ultrafiltration process unit and the second ultrafiltration process unit;
the polymer curing process unit is respectively connected with the first ion exchange process unit and the second ion exchange process unit and is used for carrying out polymer curing process 19 treatment on the waste resin generated in the first ion exchange process unit and the second ion exchange process unit (respectively passing through a node N32 and a node N33);
and the concentrated solution drying processing unit is respectively connected with the first energy-saving evaporation process unit and the second energy-saving evaporation process unit and is used for carrying out concentrated solution drying process 20 processing (respectively passing through nodes N28 and N31) on the concentrated solution generated in the first energy-saving evaporation process unit and the second energy-saving evaporation process unit.
Preferably, the first ultrafiltration process unit is further connected to a first energy efficient evaporation process unit, the first energy efficient evaporation process unit being further configured to treat the concentrate produced in the first ultrafiltration process unit (via node N27);
the second ultrafiltration process unit is also connected to a second energy efficient evaporation process unit, which is also used to treat the concentrate produced in the second ultrafiltration process unit (via node N30).
The cement fixing process unit processes waste membranes generated in the first ultrafiltration process unit and the second ultrafiltration process unit through a cement fixing process 18, the waste membranes are fixed in a steel drum through cement to form a stable steel drum waste package, and the waste package is sent to a waste warehouse for temporary storage after being processed (node N24 to node N26; node N25 to node N26); the polymer curing unit is used for treating waste resin generated in the first ion exchange process unit and the second ion exchange process unit through a polymer curing process 19, the polymer curing is carried out at normal temperature, epoxy resin-based curing agent and coagulant are mixed and then mixed with the waste resin or radioactive salt to complete the curing, the waste material anti-leaching agent has the advantages of being simple in operation, high in containment rate, good in waste material anti-leaching performance and the like, and the treated waste material is sent to a waste material warehouse for temporary storage (node N32 to node N34; node N33 to node N34); the concentrated solution drying process unit processes concentrated solutions generated by the first energy-saving evaporation process unit and the second energy-saving evaporation process unit through a concentrated solution drying process 20, dries the concentrated solutions in a steel drum, transports the dried concentrated solutions to a waste storage, loads the concentrated solutions into a concrete High Integrity Container (HIC) for temporary storage, and sends the concentrated solutions to the waste storage for temporary storage (node N28 to node N29; node N31 to node N29).
The system provided by the invention can be used for treating different types of secondary wastes by matching with different types of treatment processes, and can effectively reduce the secondary wastes and solid wastes brought by treating the secondary wastes through targeted treatment.
Preferably, the output end of the low tritium and low TDS waste liquid collecting tank is respectively connected with the low tritium and high TDS waste liquid collecting tank and the high tritium waste liquid collecting tank, the output end of the low tritium and high TDS waste liquid collecting tank is respectively connected with the high tritium waste liquid collecting tank 1 and the second ultrafiltration process unit, the output end of the low tritium waste liquid intermediate tank is also connected with the effluent discharge tank 12, and the output end of the effluent reusing tank is also connected with the effluent discharge tank 12.
Specifically, the low tritium and low TDS waste liquid collecting tank 2 and the low tritium and high TDS waste liquid collecting tank 3 are respectively connected with the high tritium waste liquid collecting tank 1 through one-way pipelines (node N11 to node N12; node N13 to node N14), that is, only the low tritium waste liquid is allowed to be discharged into the high tritium waste liquid treatment system, so that tritium pollution caused by the fact that the high tritium waste liquid enters the low tritium waste liquid treatment system is avoided.
The low tritium low TDS waste liquid collecting tank 2 is connected with the low tritium high TDS waste liquid collecting tank 3 through a one-way pipeline (through a node N15), if sampling monitoring is carried out, when TDS in low tritium waste liquid in the low tritium low TDS waste liquid collecting tank 2 is high, the low tritium high TDS waste liquid collecting tank 3 can be discharged, and enters a second energy-saving evaporation process unit to be treated by an energy-saving evaporation process 15 and then is collected in a low tritium waste liquid intermediate tank 9 (from a node N15 to a node N08 through a node N07), when TDS in low tritium waste liquid in the low tritium high TDS waste liquid collecting tank 3 is low, the low tritium high TDS waste liquid can directly enter a second ultrafiltration process unit and a second ion exchange process unit to be treated by an ultrafiltration process 5 and an ion exchange process 7 and then is collected in the low tritium waste liquid intermediate tank 9 (from a node N16 to a node N37), which the low tritium high TDS waste liquid generated in the operation of a nuclear power plant is mainly considered to be less, and the volume of low tritium low TDS waste liquid is great, consequently utilizes low tritium high TDS waste liquid collecting vat 3 as far as possible to reduce the utilization of low tritium low TDS waste liquid collecting vat 2, ensure that low tritium waste liquid processing system has sufficient collection volume to low tritium low TDS waste liquid.
The low tritium waste liquid intermediate tank 9 and the effluent reusing tank 13 are respectively connected with the effluent discharge tank 12 through one-way pipelines (node N17 to node N19, node N18, and node N18 to node N19), so that when the nuclear power plant temporarily does not need to reuse the waste liquid, and the treated waste liquid in the low tritium waste liquid intermediate tank 9 or the effluent reusing tank 13 meets the discharge standard, the waste liquid can be discharged into the effluent discharge tank 12 to be monitored and discharged.
The treatment device can treat the radioactive waste liquid generated in the operation of the nuclear power plant, and can reuse and treat secondary waste of the radioactive waste liquid of the nuclear power plant.
It will be understood that the above embodiments are merely exemplary embodiments taken to illustrate the principles of the present invention, which is not limited thereto. It will be apparent to those skilled in the art that various modifications and improvements can be made without departing from the spirit and substance of the invention, and these modifications and improvements are also considered to be within the scope of the invention.
Claims (12)
1. The method for treating the radioactive waste liquid of the nuclear power plant is characterized by comprising a waste liquid treatment and reuse method, wherein the waste liquid treatment and reuse method comprises the following steps:
dividing the radioactive waste liquid into high tritium waste liquid and low tritium waste liquid according to different tritium activity concentrations;
dividing the low tritium waste liquid into low tritium low TDS waste liquid and low tritium high TDS waste liquid according to different TDS contents, wherein in the low tritium waste liquid, the TDS less than 1000ppm is the low tritium low TDS waste liquid, and the TDS more than or equal to 1000ppm is the low tritium high TDS waste liquid;
treating the high tritium waste liquid, and monitoring the treated high tritium waste liquid to be discharged;
respectively treating the low tritium low TDS waste liquid and the low tritium high TDS waste liquid, and monitoring the treated low tritium low TDS waste liquid and the treated low tritium high TDS waste liquid for reuse and/or for discharge;
the method for treating the low tritium and low TDS waste liquid comprises the following steps:
s21, carrying out ultrafiltration process treatment on the low tritium and low TDS waste liquid;
s22, carrying out ion exchange process treatment on the low tritium and low TDS waste liquid obtained in the step S21;
the method for treating the low-tritium high-TDS waste liquid comprises the following steps:
and S31, carrying out energy-saving evaporation process treatment on the low-tritium high-TDS waste liquid.
2. The method of treating a radioactive liquid waste from a nuclear power plant according to claim 1, wherein the step of treating the high tritium liquid waste comprises:
s11, carrying out ultrafiltration process treatment on the high tritium waste liquid;
and S12, performing ion exchange process treatment on the high tritium waste liquid obtained in the step S11.
3. The method for treating the radioactive liquid waste of the nuclear power plant as claimed in claim 2, wherein before the high tritium liquid waste is treated, the high tritium liquid waste is divided into the high tritium low TDS liquid waste and the high tritium high TDS liquid waste according to different TDS contents in the high tritium liquid waste,
performing steps S11-S12 on the high tritium low TDS waste liquid;
and carrying out energy-saving evaporation process treatment on the high-tritium high-TDS waste liquid.
4. The method of claim 3, wherein the step of treating the high tritium spent solution further comprises:
s13, performing ion exchange refining treatment on the high tritium low TDS waste liquid obtained in the step S12 and/or the high tritium high TDS waste liquid obtained after the treatment of the energy-saving evaporation process;
s14, carrying out boron removal and refining treatment on the high tritium low TDS waste liquid and/or the high tritium high TDS waste liquid obtained in the step S13;
the step of treating the low tritium and low TDS waste liquid further comprises:
s23, performing ion exchange refining treatment on the low tritium and low TDS waste liquid obtained in the step S22;
s24, carrying out boron removal and refining treatment on the low tritium and low TDS waste liquid obtained in the step S23;
the step of treating the low tritium high TDS waste liquid further comprises:
s32, performing ion exchange refining treatment on the low tritium high TDS waste liquid obtained in the step S31;
and S33, performing boron removal and refining treatment on the low tritium high TDS waste liquid obtained in the step S32.
5. The method for treating a radioactive liquid waste of a nuclear power plant according to any one of claims 2 to 4, further comprising a secondary waste treatment method, the secondary waste treatment method comprising the steps of:
carrying out cement fixation process treatment on the waste membrane generated in the ultrafiltration process, and conveying the treated waste membrane to a waste storage for temporary storage;
carrying out polymer curing process treatment on waste resin generated in the ion exchange process, and conveying the treated waste resin to a waste storage for temporary storage;
and carrying out concentrated solution drying process treatment on the concentrated solution generated in the energy-saving evaporation process, and conveying the treated concentrated solution to a waste warehouse for temporary storage.
6. A radioactive waste liquid treatment system of a nuclear power plant is characterized by comprising a high tritium waste liquid treatment system and a low tritium waste liquid treatment system,
the high tritium waste liquid treatment system comprises a high tritium waste liquid collecting tank, a first ultrafiltration process unit, a first ion exchange process unit and a high tritium waste liquid middle tank which are connected in sequence,
the high tritium waste liquid collecting tank is used for collecting high tritium waste liquid;
the first ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the high tritium waste liquid;
the first ion exchange process unit is used for carrying out ion exchange process treatment on the high tritium waste liquid;
collecting the high tritium waste liquid treated by the first ion exchange process unit in a high tritium waste liquid intermediate tank;
the low tritium waste liquid treatment system comprises a low tritium and low TDS waste liquid treatment subsystem, a low tritium and high TDS waste liquid treatment subsystem and a low tritium waste liquid intermediate tank,
the low tritium and low TDS waste liquid treatment subsystem comprises a low tritium and low TDS waste liquid collecting tank, a second ultrafiltration process unit and a second ion exchange process unit which are connected in sequence,
a low tritium and low TDS waste liquid collecting tank for collecting low tritium and low TDS waste liquid, wherein TDS < 1000ppm is the low tritium and low TDS waste liquid;
the second ultrafiltration process unit is used for carrying out ultrafiltration process treatment on the low tritium and low TDS waste liquid;
the output end of the second ion exchange process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out ion exchange process treatment on the low tritium and low TDS waste liquid;
the low tritium high TDS waste liquid treatment subsystem comprises a low tritium high TDS waste liquid collecting tank and a second energy-saving evaporation process unit,
the low tritium high TDS waste liquid collecting tank is used for collecting low tritium high TDS waste liquid, and TDS (total dissolved solids) in the low tritium waste liquid is more than or equal to 1000ppm and is the low tritium high TDS waste liquid;
the input end of the second energy-saving evaporation process unit is connected with the low tritium high TDS waste liquid collecting tank, the output end of the second energy-saving evaporation process unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out energy-saving evaporation process treatment on the low tritium high TDS waste liquid,
and collecting the low tritium and low TDS waste liquid treated by the second ion exchange process unit and the low tritium and high TDS waste liquid treated by the second energy-saving evaporation process unit in a low tritium waste liquid intermediate tank.
7. The nuclear power plant radioactive spent liquor treatment system of claim 6, wherein the high tritium spent liquor collection tank includes a high tritium low TDS spent liquor collection sub-tank for collecting high tritium low TDS spent liquor and a high tritium high TDS spent liquor collection sub-tank for collecting high tritium high TDS spent liquor,
the input end of the first ultrafiltration process unit is connected with a high tritium and low TDS waste liquid collecting sub-tank in the high tritium waste liquid collecting tank,
the high tritium waste liquid treatment system also comprises a first energy-saving evaporation process unit, wherein the input end of the first energy-saving evaporation process unit is connected with the high tritium high TDS waste liquid collecting sub-tank, and the output end of the first energy-saving evaporation process unit is connected with the high tritium waste liquid middle tank and is used for carrying out energy-saving evaporation process treatment on the high tritium high TDS waste liquid.
8. The nuclear power plant radioactive liquid waste treatment system of claim 7, wherein the high tritium liquid waste treatment system further comprises a first ion exchange polishing unit, a first boron removal polishing unit and an effluent discharge tank,
the input end of the first ion exchange fine treatment unit is connected with the high tritium waste liquid intermediate tank and is used for carrying out ion exchange fine treatment on the high tritium waste liquid;
the input end of the first boron-removing fine treatment unit is connected with the first ion exchange fine treatment unit and is used for carrying out boron-removing fine treatment on the high tritium waste liquid;
and the effluent discharge tank is connected with the output end of the first ion exchange fine treatment unit and the output end of the first boron removal fine treatment unit respectively and is used for collecting the high tritium waste liquid treated by the first ion exchange fine treatment unit and the high tritium waste liquid treated by the first boron removal fine treatment unit.
9. The nuclear power plant radioactive liquid waste treatment system of claim 8, wherein the low tritium liquid waste treatment system further comprises a second ion exchange polishing unit, a second boron removal polishing unit and an effluent reusing tank,
the input end of the second ion exchange fine treatment unit is connected with the low tritium waste liquid intermediate tank and is used for carrying out ion exchange fine treatment on the low tritium waste liquid;
the input end of the second boron-removing fine treatment unit is connected with the second ion exchange fine treatment unit and is used for carrying out boron-removing fine treatment on the low tritium waste liquid;
and the effluent multiplexing tank is connected with the output end of the second ion exchange fine treatment unit and the output end of the second boron removal fine treatment unit and is used for collecting the low tritium waste liquid treated by the second ion exchange fine treatment unit and the low tritium waste liquid treated by the second boron removal fine treatment unit.
10. The nuclear power plant radioactive liquid waste treatment system of claim 9, further comprising a secondary waste treatment system including a cement fixation process unit, a polymer solidification process unit, and a concentrate drying process unit,
the cement fixing process unit is respectively connected with the first ultrafiltration process unit and the second ultrafiltration process unit and is used for carrying out cement fixing process treatment on waste membranes generated in the first ultrafiltration process unit and the second ultrafiltration process unit;
the polymer curing process unit is respectively connected with the first ion exchange process unit and the second ion exchange process unit and is used for carrying out polymer curing process treatment on the waste resin generated in the first ion exchange process unit and the second ion exchange process unit;
and the concentrated solution drying treatment unit is respectively connected with the first energy-saving evaporation process unit and the second energy-saving evaporation process unit and is used for carrying out concentrated solution drying treatment on concentrated solutions generated in the first energy-saving evaporation process unit and the second energy-saving evaporation process unit.
11. The nuclear power plant radioactive liquid waste treatment system of claim 10, wherein the first ultrafiltration process unit is further connected to a first energy efficient evaporation process unit, the first energy efficient evaporation process unit being further configured to treat a concentrate produced in the first ultrafiltration process unit;
the second ultrafiltration process unit is also connected with the second energy-saving evaporation process unit, and the second energy-saving evaporation process unit is also used for treating the concentrated solution generated in the second ultrafiltration process unit.
12. The nuclear power plant radioactive liquid waste treatment system of claim 11, wherein the output of the low tritium low TDS liquid waste collection tank is further connected to a low tritium high TDS liquid waste collection tank and a high tritium liquid waste collection tank, respectively,
the output end of the low tritium high TDS waste liquid collecting tank is also respectively connected with the high tritium waste liquid collecting tank and the second ultrafiltration process unit,
the output end of the low tritium waste liquid intermediate tank is also connected with an effluent discharge tank,
the output end of the effluent multiplexing tank is also connected with an effluent discharge tank.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811390279.3A CN109524143B (en) | 2018-11-21 | 2018-11-21 | Method and system for treating radioactive waste liquid of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811390279.3A CN109524143B (en) | 2018-11-21 | 2018-11-21 | Method and system for treating radioactive waste liquid of nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109524143A CN109524143A (en) | 2019-03-26 |
| CN109524143B true CN109524143B (en) | 2020-10-20 |
Family
ID=65776648
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811390279.3A Active CN109524143B (en) | 2018-11-21 | 2018-11-21 | Method and system for treating radioactive waste liquid of nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109524143B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112340884A (en) * | 2020-11-06 | 2021-02-09 | 北京清核朝华科技有限公司 | Novel radioactive waste liquid treatment system and method for TEU system of nuclear power plant |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56153297A (en) * | 1980-04-30 | 1981-11-27 | Sumitomo Heavy Industries | Method of processing ionexchange resin waste in heavy water moderated reactor |
| JPH0519095A (en) * | 1991-07-10 | 1993-01-26 | Hitachi Ltd | Disposing method for tritium contaminated gas |
| CN104900283A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A nuclear power plant radioactive liquid waste treatment system |
| CN104900284A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A treatment system for nuclear power plant radioactive waste liquid reuse |
| CN105244068A (en) * | 2015-08-31 | 2016-01-13 | 中国核电工程有限公司 | Device and method for treating high-salt content radioactive waste liquid |
| CN105702309A (en) * | 2016-04-20 | 2016-06-22 | 中国工程物理研究院材料研究所 | SPE (Solid Polymer Electrolyte) electrolysis system used for tritium concentration and realization method for electrolysis system |
| CN107170505A (en) * | 2017-06-29 | 2017-09-15 | 江苏金环环保设备有限公司 | The composite processing system and method for a kind of nuclear power plant's boron-containing radioactive waste liquid |
-
2018
- 2018-11-21 CN CN201811390279.3A patent/CN109524143B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56153297A (en) * | 1980-04-30 | 1981-11-27 | Sumitomo Heavy Industries | Method of processing ionexchange resin waste in heavy water moderated reactor |
| JPH0519095A (en) * | 1991-07-10 | 1993-01-26 | Hitachi Ltd | Disposing method for tritium contaminated gas |
| CN104900283A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A nuclear power plant radioactive liquid waste treatment system |
| CN104900284A (en) * | 2015-04-03 | 2015-09-09 | 中国核电工程有限公司 | A treatment system for nuclear power plant radioactive waste liquid reuse |
| CN105244068A (en) * | 2015-08-31 | 2016-01-13 | 中国核电工程有限公司 | Device and method for treating high-salt content radioactive waste liquid |
| CN105702309A (en) * | 2016-04-20 | 2016-06-22 | 中国工程物理研究院材料研究所 | SPE (Solid Polymer Electrolyte) electrolysis system used for tritium concentration and realization method for electrolysis system |
| CN107170505A (en) * | 2017-06-29 | 2017-09-15 | 江苏金环环保设备有限公司 | The composite processing system and method for a kind of nuclear power plant's boron-containing radioactive waste liquid |
Non-Patent Citations (2)
| Title |
|---|
| AP1000核电机组液态流出物复用与排放;邓治国 等;《辐射防护通讯》;20151031;第35卷(第5期);第21-24页 * |
| 韩国的放射性废物管理;郭志锋;《国外核新闻》;20040331;第24-25页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109524143A (en) | 2019-03-26 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104900283B (en) | A kind of nuclear power plant's Liquid Radwaste Treatment | |
| CN203773964U (en) | Comprehensive waste liquid treatment system for waste treatment system of nuclear power station | |
| CN109524143B (en) | Method and system for treating radioactive waste liquid of nuclear power plant | |
| CN108257706A (en) | A kind of uranium-containing waste water processing method | |
| CN107195352A (en) | A kind of nuclear power plant's radioactive liquid waste and its secondary waste treatment system | |
| CN102768870A (en) | Method and system for reusing liquid waste in pressurized water reactor nuclear power station | |
| Song et al. | A study on the applicability for primary system decontamination through analysis on NPP decommission technology and international experience | |
| CN109036611A (en) | Nuclear steam generator cleans the processing method of waste liquid and Spent Radioactive organic solvent | |
| JP2002341088A (en) | Treating method of activated concrete | |
| Korchagin et al. | Improvement of technology for treatment of spent radioactive ion-exchange resins at nuclear power stations | |
| KR20180040017A (en) | Electrolytic decontamination method capable of regenerative electrolyte | |
| CN104900284B (en) | A kind of processing system for nuclear power plant's radioactive liquid waste multiplexing | |
| CN110491540B (en) | Method for treating radioactive waste | |
| CN211507146U (en) | System for adopt adsorbing material to carry out nuclear power station radioactive waste liquid treatment | |
| JP2509654B2 (en) | Chemical decontamination waste liquid treatment method | |
| JPH09189798A (en) | Radioactive waste liquid treatment device | |
| JP2000140839A (en) | Desalting device of condensate | |
| Penzin et al. | Development of Technologies for Handling Liquid Radioactive Waste of Nuclear Power Plants | |
| CN217230291U (en) | High-concentration organic wastewater treatment system | |
| Cha et al. | A Study on the Status of Multi-nuclide Removal System (ALPS) and Dilution/Discharge Process on Fukushima NPP Site | |
| JPS5855779A (en) | Sample concentrating device for measuring density of ultralow radioactivity | |
| Yoon et al. | Analysis on the Current Status of Chemical Decontamination Technology of Steam Generators in the Oversea Nuclear Power Plants (NPPs) | |
| Shin et al. | Development of Automated Liquid Radioactive Waste Pre-treatment Device at KAERI | |
| Bushart et al. | The EPRI DFDX chemical decontamination process | |
| JPS604895A (en) | Electrolytic decontaminating waste liquor regenerating treating device |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |