A radioactive waste sodium treatment system and method
By converting solid radioactive waste sodium into liquid and reacting with water vapor, combining multi-layer partitions and mixed gas systems, the safety hazards in radioactive waste sodium treatment are solved, the stability and safe treatment of radioactive waste is achieved, and nuclear power is improved The level of waste management in the factory.
Patent Information
- Application Number
- CN202110665592.9
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- Filing Date
- 2021-06-16
- Publication Date
- 2024-12-13
- Estimated Expiration
- 2041-06-16
AI Technical Summary
In the prior art, radioactive waste sodium treatment has safety risks, especially the violent reactivity of metal sodium leads to unstable treatment, which may cause explosion and combustion, and temporary storage treatments have great risks.
A system including radioactive waste sodium pretreatment, treatment, gas treatment and liquid treatment units is designed to control the reaction speed by converting solid radioactive waste sodium into liquid and reacting with water vapor, using a multi-layer partition structure and a mixed gas System, ensures safe reactions and ensures safe emissions of waste gas and waste liquids through efficient filtration and monitoring.
It improves the safety and reliability of radioactive waste sodium treatment, prevents hydrogen explosion, ensures the stable treatment of radioactive waste, reduces safety hazards during the treatment process, and enhances the level of radioactive waste management in nuclear power plants.
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Figure CN113409978B_ABST
Abstract
Description
Technical Field
[0001] The invention relates to the technical field of radioactive waste treatment, and in particular to a system and method for treating radioactive waste sodium. Background Art
[0002] Sodium-cooled fast reactors use liquid sodium metal as a coolant. During operation, sodium-cooled fast reactor units will produce a certain amount of radioactive waste sodium, which mainly comes from the sodium remaining in the replacement and removal of equipment during the maintenance of sodium circuit equipment, as well as the sodium produced during the sampling process of the sodium circuit. A large amount of radioactive waste sodium will also be produced during the decommissioning of fast reactor units. Radioactive waste sodium is not only radioactive, but also has the following characteristics of metallic sodium: metallic sodium is one of the most active metal elements, and metallic sodium easily reacts chemically with water and oxygen in the air; sodium reacts with water to produce strong alkali sodium hydroxide and hydrogen, the reaction is very violent, and is accompanied by the release of a large amount of heat. The reaction product hydrogen may explode when the concentration in the air exceeds 4%; sodium reacts with oxygen to produce a variety of oxides. It is generally believed that when the temperature is higher than 110 to 130 degrees Celsius, sodium will burn; sodium combustion will produce a large amount of sodium aerosol, which mainly has a certain impact on human skin and respiratory system. Therefore, the radioactive waste sodium generated during the operation and decommissioning of the unit needs to take certain treatment measures to convert it into a stable state for proper and safe disposal, otherwise there will be a major safety hazard.
[0003] At present, non-radioactive sodium is generally treated in China by reprocessing in sodium recovery plants and incineration disposal. Radioactive waste sodium is treated by temporary storage. However, due to the special properties of metallic sodium, temporary storage treatment poses a great safety hazard. Summary of the invention
[0004] Based on this, it is necessary to provide a radioactive waste sodium treatment system and method to address the safety risks of existing radioactive waste sodium treatment, so as to solve the problem of radioactive waste sodium treatment, improve the level of radioactive waste safety management in nuclear power plants, and minimize radioactive waste.
[0005] In order to achieve the above object, the present invention provides the following technical solutions:
[0006] A radioactive waste sodium treatment system, comprising a radioactive waste sodium pretreatment unit, a radioactive waste sodium treatment unit, a radioactive waste gas treatment unit and a radioactive waste liquid treatment unit;
[0007] The radioactive waste sodium pretreatment unit is connected to the radioactive waste sodium treatment unit through a pipeline, and the radioactive waste sodium treatment unit is respectively connected to the radioactive waste gas treatment unit and the radioactive waste liquid treatment unit through pipelines;
[0008] The radioactive waste sodium pretreatment unit converts the radioactive waste sodium to be treated from solid to liquid, and then filters and transports it to the radioactive waste sodium treatment unit;
[0009] The radioactive waste sodium treatment unit controls the reaction of radioactive waste sodium with water vapor, and the radioactive waste liquid after the reaction is transported to the radioactive waste liquid treatment unit, and the radioactive waste gas after the reaction is transported to the radioactive waste gas treatment unit;
[0010] The radioactive waste liquid treatment unit stores the radioactive waste liquid to a certain liquid level and then discharges it;
[0011] The radioactive waste gas treatment unit circulates and filters the radioactive waste gas until it meets the radioactive waste gas emission standards before discharging it.
[0012] Furthermore, the radioactive waste sodium pretreatment unit comprises a radioactive waste sodium temporary storage container, a radioactive waste sodium filter, a radioactive waste sodium delivery pump and a radioactive waste sodium barrel heating device;
[0013] The radioactive waste sodium treatment unit comprises a radioactive waste sodium injection device, a radioactive waste sodium reactor, a desalted water system, a water vapor system and a mixed gas system;
[0014] The radioactive liquid waste treatment unit comprises a waste liquid discharge pump and a waste liquid collection tank;
[0015] The radioactive waste gas treatment unit includes a waste gas filtering mechanism, a waste gas exhaust fan and a radioactivity measuring instrument;
[0016] The radioactive sodium waste temporary storage container is placed on the radioactive sodium waste barrel heating device;
[0017] The radioactive sodium waste temporary storage container is connected to the radioactive sodium waste filter, the radioactive sodium waste delivery pump and the radioactive sodium waste injection device in sequence through pipelines;
[0018] The radioactive waste sodium spray device is suspended in the radioactive waste sodium reactor;
[0019] The upper part of the radioactive sodium waste reactor is connected to the inlet of the exhaust gas filtration mechanism and the desalted water system through pipelines, the middle part of the radioactive sodium waste reactor is connected to the water vapor system and the mixed gas system through pipelines, and the bottom of the radioactive sodium waste reactor is connected to the waste liquid discharge pump and the waste liquid collection tank in sequence through pipelines;
[0020] The outlet of the exhaust gas filtering mechanism is connected to the exhaust gas exhaust fan and the radioactivity measuring instrument in sequence through pipelines.
[0021] Furthermore, the radioactive waste sodium treatment unit also includes a steam-water separator and a cooling water system. The upper side of the radioactive waste sodium reactor is connected to the steam-water separator through a pipeline, the condensate side of the steam-water separator is connected to the waste liquid collection tank through a pipeline, the cooling water side of the steam-water separator is connected to the cooling water system through a pipeline, and the gas side of the steam-water separator is connected to the inlet of the exhaust gas filtering mechanism through a pipeline.
[0022] Furthermore, a front isolation valve of the radioactive waste sodium filter is arranged on the pipeline connecting the radioactive waste sodium temporary storage container and the radioactive waste sodium filter, a rear isolation valve of the radioactive waste sodium filter is arranged on the pipeline connecting the radioactive waste sodium filter and the radioactive waste sodium delivery pump, and a pressure gauge B and an inlet valve of the radioactive waste sodium reactor are arranged in sequence on the pipeline connecting the radioactive waste sodium delivery pump and the radioactive waste sodium injection device.
[0023] Furthermore, the radioactive waste sodium pretreatment unit also includes a radioactive waste sodium delivery pipeline heating device for heating the pipeline connecting the radioactive waste sodium temporary storage container, the radioactive waste sodium delivery pump, and the radioactive waste sodium injection device.
[0024] Furthermore, a heating and heat preservation device is provided on the outer surface of the pipeline connecting the inlet valve of the radioactive waste sodium reactor and the radioactive waste sodium injection device.
[0025] Furthermore, the radioactive waste sodium pretreatment unit also includes an argon storage tank, which is connected to the radioactive waste sodium temporary storage container and the radioactive waste sodium reactor through pipelines.
[0026] Furthermore, an argon storage tank outlet isolation valve is provided at the argon storage tank outlet, and the argon storage tank outlet isolation valve is connected to the radioactive waste sodium temporary storage container and the radioactive waste sodium reactor through pipelines, respectively; an argon inlet isolation valve for the waste sodium temporary storage container is provided on the pipeline connecting the argon storage tank outlet isolation valve and the radioactive waste sodium temporary storage container, and a pressure gauge A and an argon inlet isolation valve for the radioactive waste sodium reactor are sequentially provided on the pipeline connecting the argon storage tank outlet isolation valve and the radioactive waste sodium reactor.
[0027] Furthermore, a desalted water inlet isolation valve is provided on the pipeline connecting the radioactive waste sodium reactor and the desalted water system.
[0028] Furthermore, a water vapor inlet isolation valve A and a water vapor inlet isolation valve B are arranged on the pipeline connecting the radioactive waste sodium reactor and the water vapor system.
[0029] Furthermore, the radioactive waste sodium processing unit also includes a pressure gauge D, a thermometer, a hydrogen meter and a liquid level gauge, and the pressure gauge D, the thermometer, the hydrogen meter and the liquid level gauge are respectively installed on the top of the radioactive waste sodium reactor through pipelines.
[0030] Furthermore, the mixed gas system includes a nitrogen storage tank and a carbon dioxide storage tank, and the outlets of the nitrogen storage tank and the carbon dioxide storage tank are combined into a mixed gas outlet and connected to the radioactive waste sodium reactor.
[0031] Furthermore, a nitrogen storage tank outlet isolation valve is provided at the outlet of the nitrogen storage tank, a carbon dioxide gas storage tank outlet isolation valve is provided at the outlet of the carbon dioxide gas storage tank, and a pressure gauge C and a radioactive waste sodium reactor gas inlet isolation valve are sequentially provided on the pipeline connecting the mixed gas outlet and the radioactive waste sodium reactor.
[0032] Furthermore, a gas discharge outlet valve is arranged on the pipeline connecting the radioactive waste sodium reactor and the steam-water separator.
[0033] Furthermore, the exhaust gas filtering mechanism includes two exhaust gas filters A and B connected in parallel.
[0034] Furthermore, an isolation valve A is arranged on the pipeline connecting the exhaust gas filtering mechanism and the radioactive waste sodium reactor, an isolation valve B is arranged on the pipeline connecting the exhaust gas filtering mechanism and the steam-water separator, an exhaust gas filter A inlet isolation valve is arranged at the inlet of the exhaust gas filter A, an exhaust gas filter A outlet isolation valve is arranged at the outlet of the exhaust gas filter A, an exhaust gas filter B inlet isolation valve is arranged at the inlet of the exhaust gas filter B, an exhaust gas filter B outlet isolation valve is arranged at the outlet of the exhaust gas filter B, an exhaust gas exhaust fan outlet isolation valve is arranged at the outlet of the exhaust gas filter B, an isolation valve C is arranged between the inlet of the exhaust gas filtering mechanism and the exhaust gas exhaust fan outlet isolation valve through a pipeline, the exhaust gas exhaust fan outlet isolation valve is connected to the plant ventilation system through a pipeline, and a radioactive measuring instrument and an exhaust gas exhaust valve are arranged in sequence on the pipeline connecting the exhaust gas exhaust fan outlet isolation valve and the plant ventilation system.
[0035] Furthermore, a cooling water inlet valve is provided at the inlet of the cooling water system, a cooling water outlet valve is provided at the outlet of the cooling water system, and the cooling water side of the steam-water separator is connected to the cooling water inlet valve and the cooling water outlet valve respectively through pipelines.
[0036] Furthermore, a waste liquid discharge valve is arranged on the pipeline connecting the radioactive waste sodium reactor and the waste liquid discharge pump, a waste liquid discharge pump outlet valve is arranged at the outlet of the waste liquid discharge pump, a steam-water separator outlet valve is arranged at the condensate side connected to the steam-water separator, a waste liquid collection tank inlet isolation valve is arranged at the inlet of the waste liquid collection tank, and the waste liquid discharge pump outlet valve and the steam-water separator outlet valve are both connected to the waste liquid collection tank inlet isolation valve through pipelines.
[0037] Furthermore, the valves of the radioactive waste sodium treatment system are electric valves, and the control is performed automatically by PLC. The PLC control uses Siemens S7.0 version to program the electric valves in the system to achieve automatic operation and control of the system.
[0038] A method for treating radioactive sodium waste comprises the following steps: converting the radioactive sodium waste to be treated from solid to liquid, filtering and reacting with water vapor; during the reaction, controlling the reaction speed of the radioactive sodium waste and water vapor; after the radioactive waste gas after the reaction is separated from gas and liquid, the gas is circulated and filtered to meet the radioactive waste gas emission standard and then discharged to the ventilation system of the plant where the system is located; and the liquid and the radioactive waste liquid after the reaction are stored to a certain liquid level and then discharged into the radioactive waste liquid treatment system of the power station.
[0039] Furthermore, the method for treating radioactive waste sodium specifically comprises the following steps:
[0040] 1. The radioactive waste sodium treatment system automatically controls the exhaust gas exhaust fan to evacuate the radioactive waste sodium reactor;
[0041] 2. The radioactive waste sodium heating device automatically controls the heating of the radioactive waste sodium to 110 degrees Celsius - 120 degrees Celsius, and the radioactive waste sodium transportation pipeline heating device automatically controls the heating of the radioactive waste sodium transportation pipeline to 110 degrees Celsius - 120 degrees Celsius;
[0042] 3. Start the radioactive waste sodium delivery pump, and the liquid radioactive waste sodium passes through the radioactive waste sodium filter and then is sprayed onto the partition in the reactor through the waste sodium spraying device;
[0043] 4. The radioactive waste sodium treatment system automatically monitors the gas concentration of the mixed gas, and automatically injects gas into the radioactive waste sodium reactor according to the hydrogen concentration, automatically controls the water vapor inlet valve A and the water vapor inlet isolation valve B, and injects water vapor into the radioactive waste sodium reactor according to the hydrogen monitoring results, so that the radioactive waste sodium in the radioactive waste sodium reactor reacts fully with the water vapor;
[0044] 5. The radioactive waste gas after the automatic control reaction of the radioactive waste sodium treatment system is circulated and filtered through the waste gas filtration mechanism until it passes the detection of the radioactivity measurement instrument, and then discharged into the ventilation system of the plant where the system is located through the waste gas exhaust fan;
[0045] 6. The radioactive waste sodium treatment system automatically controls the desalted water inlet valve and injects desalted water into the radioactive waste sodium reactor;
[0046] 7. The radioactive sodium waste treatment system automatically controls the waste liquid discharge pump to discharge the radioactive waste liquid after the reaction into the waste liquid collection tank; the radioactive sodium waste treatment system automatically controls the waste liquid collection tank to discharge the radioactive waste liquid in the waste liquid collection tank to the radioactive waste liquid treatment system of the power station.
[0047] Furthermore, the radioactive waste sodium treatment system automatically controls the injection of the radioactive waste gas after the reaction into the steam-water separator, automatically controls the cooling water system to inject cooling water into the steam-water separator, automatically controls the waste gas filtering mechanism to filter the radioactive waste gas after the reaction, automatically controls the gas after the steam-liquid separation of the steam-water separator to be circulated and filtered through the waste gas filtering mechanism until it is qualified after being detected by the radioactive measuring instrument and discharged into the ventilation system of the plant where the system is located, and automatically controls the liquid after the steam-liquid separation of the steam-water separator to be discharged into the waste liquid collection tank.
[0048] The beneficial technical effects of the present invention are:
[0049] The radioactive sodium waste treatment system of the present invention comprises a radioactive sodium waste pretreatment unit, a radioactive sodium waste treatment unit, a radioactive waste liquid treatment unit and a radioactive waste gas treatment unit. The radioactive sodium waste pretreatment unit first converts the radioactive sodium waste from a solid state into a liquid state before transporting it, thereby improving the feasibility and safety of radioactive sodium waste treatment; a radioactive sodium waste filter is provided to filter impurities in the liquid radioactive sodium waste to avoid clogging of a radioactive sodium waste injection device, thereby improving the safety and reliability of the radioactive sodium waste treatment system; an electric heating and heat preservation device is arranged on the radioactive sodium waste transportation pipeline, and an electric heating device is arranged on the injection device, thereby maintaining a constant temperature during the transmission of the radioactive sodium waste, thereby preventing clogging of the transportation pipeline and the injection device, thereby improving the safety and reliability of the radioactive sodium waste treatment system;
[0050] A radioactive sodium waste injection device is designed inside the reactor. The injection device is fixed to the top of the reactor by pipeline welding and connected to the inlet valve of the radioactive sodium waste reactor. The device will spray the radioactive sodium waste evenly in the reactor under pressure, increase the effective area of the radioactive sodium waste and the reaction medium, effectively control the reaction speed of the radioactive sodium waste, and improve the safety of radioactive sodium waste treatment;
[0051] Partitions A, B and C with different apertures are designed inside the reactor. Each layer of partitions is designed into a grid structure with different apertures. The aperture of partition A is 2 mm, the aperture of partition B is 1.5 mm, and the aperture of partition C is 1 mm. The partitions are made of 1 cm thick stainless steel. The partitions are respectively fixed on the partition support blocks A, B and C in the reactor by welding, so that the radioactive waste sodium flows on different partitions after being sprayed and is evenly distributed, reducing the particle diameter of the radioactive waste sodium in the reactor and increasing the effective area of the radioactive waste sodium and the reaction medium, which can effectively control the reaction speed of the radioactive waste sodium and improve the safety of the treatment of the radioactive waste sodium;
[0052] The treatment process adopts a water vapor + nitrogen treatment process. The water vapor inlet pipelines are respectively arranged at the upper part of the partition A and the lower part of the partition B, and the mixed gas inlet pipeline is arranged at the lower part of the partition A. The reaction rate with the radioactive waste sodium is controlled by controlling the flow rate of water vapor entering the reactor. At the same time, the injection amount of water vapor and nitrogen is controlled by detecting the concentration of hydrogen in the reactor to control the speed of the sodium-water reaction, thereby preventing the occurrence of hydrogen explosion and improving the safety of the system.
[0053] The radioactive waste gas treatment unit has two high-efficiency filters in parallel design, one for backup and the other for use, to filter and monitor the radioactive waste gas generated during the treatment of radioactive waste sodium, and discharge it after it passes the monitoring. At the same time, the waste gas return pipeline is designed. When the radioactive waste gas monitoring fails, the valve on the return pipeline is opened and the outlet isolation valve is closed, so that the gas is circulated and filtered through the filter, and discharged after it passes the monitoring, which greatly ensures the safety of the environment and improves the safety of the system.
[0054] The radioactive liquid waste treatment unit collects the radioactive liquid waste generated during the treatment of radioactive waste sodium and incorporates it into the power plant's radioactive liquid waste treatment system for treatment, ensuring environmental safety and improving the safety of the system. BRIEF DESCRIPTION OF THE DRAWINGS
[0055] Figure 1 It is a schematic structural diagram of the radioactive waste sodium treatment system of the present invention;
[0056] Figure 2 It is a schematic diagram of the structure of the radioactive waste sodium reactor of the present invention.
[0057] In the figure, 1, radioactive sodium waste temporary storage container; 2, isolation valve before radioactive sodium waste filter; 3, radioactive sodium waste filter; 4, isolation valve after radioactive sodium waste filter; 5, radioactive sodium waste delivery pump; 6, radioactive sodium waste reactor inlet valve; 7, radioactive sodium waste barrel heating device; 8, argon storage tank; 9, argon storage tank outlet isolation valve; 10, argon inlet isolation valve of waste sodium temporary storage container; 11, argon inlet isolation valve of radioactive sodium waste reactor; 12, pressure gauge A; 13, pressure gauge A; 14, pressure gauge B; 15, pressure gauge C; 16, pressure gauge A; 17, pressure gauge B; 18, pressure gauge C; 19, pressure gauge A; 20, pressure gauge B; 21, pressure gauge C; 22, pressure gauge A; 23, pressure gauge B; 24, pressure gauge C; 25, pressure gauge A; 26, pressure gauge B; 27, pressure gauge A; 28, pressure gauge B; 29, pressure gauge A; 30, pressure gauge B; 31, pressure gauge A; 32, pressure gauge B; 33, pressure gauge A; 34, pressure gauge B; 35, pressure gauge A; 36, pressure gauge B; 37, pressure gauge A; 38, pressure gauge B; 39, pressure gauge A; 40, pressure gauge B; 41, pressure gauge A; 42, pressure gauge B; 43, pressure gauge A; 44, pressure gauge B; 45, pressure gauge A; 46, pressure gauge B; 47, pressure gauge A; 48, pressure gauge B; 49, pressure gauge B; 50, pressure gauge A; 49, pressure gauge B; 51, pressure gauge A; 40, pressure gauge B; 41, pressure gauge A Pressure gauge B; 14. Radioactive waste sodium injection device; 15. Radioactive waste sodium reactor; 16. Nitrogen storage tank; 17. Gas storage tank; 18. Nitrogen storage tank outlet isolation valve; 19. Gas storage tank outlet isolation valve; 20. Radioactive waste sodium reactor gas inlet isolation valve; 21. Steam inlet isolation valve A; 22. Desalted water inlet isolation valve; 23. Pressure gauge C; 24. Pressure gauge D; 25. Thermometer; 26. Hydrogen meter; 27. Liquid level gauge; 28. Gas discharge outlet valve; 29, steam-water separator; 30, steam-water separator outlet valve; 31, waste liquid discharge valve; 32, waste liquid discharge pump; 33, waste liquid discharge pump outlet valve; 34, waste liquid collection tank inlet isolation valve; 35, waste liquid collection tank; 36, waste liquid collection tank outlet isolation valve; 37, cooling water inlet valve; 38, cooling water outlet valve; 39, isolation valve A; 40, isolation valve B; 41, exhaust gas filter A inlet isolation valve; 42, exhaust gas filter A; 43, exhaust gas filter A outlet isolation valve Isolation valve; 44. Exhaust filter B inlet isolation valve; 45. Exhaust filter B; 46. Exhaust filter B outlet isolation valve; 47. Exhaust exhaust fan; 48. Exhaust exhaust fan outlet isolation valve; 49. Exhaust exhaust valve; 50. Isolation valve C; 51. Radioactive measuring instrument; 52. Heating and insulation device; 53. Water vapor inlet isolation valve B; 54. Partition A; 55. Partition B; 56. Partition C; 57. Support block A; 58. Support block B; 59. Support block C. DETAILED DESCRIPTION
[0058] In the description of the present invention, it is necessary to understand that the orientations or positional relationships indicated by terms such as “left end”, “right end”, “above”, “below”, “outside”, “inside”, etc. are based on the orientations or positional relationships shown in the accompanying drawings, and are only for the convenience of describing the present invention and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as a limitation on the present invention.
[0059] A radioactive waste sodium treatment system, comprising a radioactive waste sodium pretreatment unit, a radioactive waste sodium treatment unit, a radioactive waste gas treatment unit and a radioactive waste liquid treatment unit;
[0060] The radioactive waste sodium pretreatment unit is connected to the radioactive waste sodium treatment unit through a pipeline, and the radioactive waste sodium treatment unit is respectively connected to the radioactive waste gas treatment unit and the radioactive waste liquid treatment unit through pipelines;
[0061] The radioactive waste sodium pretreatment unit converts the radioactive waste sodium to be treated from solid to liquid, and then filters and transports it to the radioactive waste sodium treatment unit;
[0062] The radioactive waste sodium treatment unit controls the reaction of radioactive waste sodium with water vapor, and the radioactive waste liquid after the reaction is transported to the radioactive waste liquid treatment unit; after the radioactive waste gas after the reaction is separated into gas and liquid, the gas is transported to the radioactive waste gas treatment unit, and the liquid is transported to the radioactive waste liquid treatment unit;
[0063] The radioactive liquid waste treatment unit stores the radioactive liquid waste to a certain liquid level and then discharges it into the radioactive liquid waste treatment system of the power station;
[0064] The radioactive waste gas treatment unit circulates and filters the radioactive waste gas until it meets the radioactive waste gas emission standards and then discharges it into the ventilation system of the plant where the system is located.
[0065] Furthermore, the radioactive waste sodium pretreatment unit comprises a radioactive waste sodium temporary storage container 1, a radioactive waste sodium filter 3, a radioactive waste sodium delivery pump 5 and a radioactive waste sodium barrel heating device 7;
[0066] The radioactive waste sodium treatment unit comprises a radioactive waste sodium injection device 14, a radioactive waste sodium reactor 15, a desalted water system, a water vapor system and a mixed gas system;
[0067] The radioactive liquid waste treatment unit comprises a waste liquid discharge pump 32 and a waste liquid collection tank 35;
[0068] The radioactive waste gas treatment unit includes a waste gas filtering mechanism, a waste gas exhaust fan 47 and a radioactivity measuring instrument 51;
[0069] The radioactive sodium waste temporary storage container 1 is placed on the radioactive sodium waste barrel heating device 7;
[0070] The radioactive waste sodium temporary storage container 1 is connected to the radioactive waste sodium filter 3, the radioactive waste sodium delivery pump 5 and the radioactive waste sodium injection device 14 in sequence through pipelines;
[0071] The radioactive waste sodium spray device 14 is suspended in the radioactive waste sodium reactor 15;
[0072] The upper part of the radioactive sodium waste reactor 15 is connected to the inlet of the exhaust gas filtering mechanism and the desalted water system through pipelines, the middle part of the radioactive sodium waste reactor 15 is connected to the water vapor system and the mixed gas system through pipelines, and the bottom of the radioactive sodium waste reactor 15 is connected to the waste liquid discharge pump 32 and the waste liquid collection tank 35 in sequence through pipelines;
[0073] The outlet of the exhaust gas filtering mechanism is connected to the exhaust gas exhaust fan 47 and the radioactivity measuring instrument 51 in sequence through pipelines.
[0074] Furthermore, the radioactive waste sodium treatment unit also includes a steam-water separator 29 and a cooling water system. The upper side of the radioactive waste sodium reactor 15 is connected to the steam-water separator 29 through a pipeline, the condensate side of the steam-water separator 29 is connected to the waste liquid collection tank 35 through a pipeline, the cooling water side of the steam-water separator 29 is connected to the cooling water system through a pipeline, and the gas side of the steam-water separator 29 is connected to the inlet of the exhaust gas filtering mechanism through a pipeline.
[0075] Furthermore, a radioactive waste sodium filter front isolation valve 2 is arranged on the pipeline connecting the radioactive waste sodium temporary storage container 1 and the radioactive waste sodium filter 3, a radioactive waste sodium filter rear isolation valve 4 is arranged on the pipeline connecting the radioactive waste sodium filter 3 and the radioactive waste sodium delivery pump 5, and a pressure gauge B13 and a radioactive waste sodium reactor inlet valve 6 are arranged in sequence on the pipeline connecting the radioactive waste sodium delivery pump 5 and the radioactive waste sodium injection device 14.
[0076] Furthermore, the radioactive waste sodium pretreatment unit further includes a radioactive waste sodium delivery pipeline heating device for heating the pipeline connecting the radioactive waste sodium temporary storage container 1 , the radioactive waste sodium delivery pump 5 , and the radioactive waste sodium injection device 14 .
[0077] Furthermore, a heating and heat preservation device 52 is provided on the outer surface of the pipeline connecting the radioactive waste sodium reactor inlet valve 6 and the radioactive waste sodium injection device 14 .
[0078] Furthermore, the radioactive waste sodium pretreatment unit also includes an argon storage tank 8, which is connected to the radioactive waste sodium temporary storage container 1 and the radioactive waste sodium reactor 15 through pipelines. When the radioactive waste sodium is not treated, by opening the argon storage tank outlet isolation valve 9, the waste sodium temporary storage container argon inlet isolation valve 10, and the radioactive waste sodium reactor argon inlet isolation valve 11, argon is respectively filled into the radioactive waste sodium temporary storage container 1 and the radioactive waste sodium reactor 15 to prevent the radioactive sodium from reacting, protect the radioactive sodium in the tank, and play a safe storage function.
[0079] Furthermore, an argon storage tank outlet isolation valve 9 is provided at the outlet of the argon storage tank 8, and the argon storage tank outlet isolation valve 9 is respectively connected to the radioactive waste sodium temporary storage container 1 and the radioactive waste sodium reactor 15 through pipelines, and a waste sodium temporary storage container argon inlet isolation valve 10 is provided on the pipeline connecting the argon storage tank outlet isolation valve 9 and the radioactive waste sodium temporary storage container 1, and a pressure gauge A12 and a radioactive waste sodium reactor argon inlet isolation valve 11 are sequentially provided on the pipeline connecting the argon storage tank outlet isolation valve 9 and the radioactive waste sodium reactor 15.
[0080] Furthermore, a desalted water inlet isolation valve 22 is provided on the pipeline connecting the radioactive waste sodium reactor 15 and the desalted water system.
[0081] Furthermore, a water vapor inlet isolation valve A 21 and a water vapor inlet isolation valve B 53 are provided at the water vapor system inlet.
[0082] Furthermore, the radioactive waste sodium processing unit also includes a pressure gauge D24, a thermometer 25, a hydrogen meter 26 and a liquid level gauge 27, which are respectively installed on the top of the radioactive waste sodium reactor 15 through pipelines to measure the pressure, temperature, hydrogen content and liquid level in the radioactive waste sodium reactor 15 in real time.
[0083] Furthermore, the mixed gas system includes a nitrogen storage tank 16 and a carbon dioxide storage tank 17 , and the outlets of the nitrogen storage tank 16 and the carbon dioxide storage tank 17 are combined into a mixed gas outlet and connected to the radioactive waste sodium reactor 15 .
[0084] Furthermore, a nitrogen storage tank outlet isolation valve 18 is provided at the outlet of the nitrogen storage tank 16, and a carbon dioxide gas storage tank outlet isolation valve 19 is provided at the outlet of the carbon dioxide gas storage tank 17. The nitrogen storage tank outlet isolation valve 18 and the carbon dioxide gas storage tank outlet isolation valve 19 are connected to the radioactive waste sodium reactor gas inlet isolation valve 20 through pipelines, and pressure gauges C23 are arranged in sequence on the connected pipelines.
[0085] Furthermore, a gas discharge outlet valve 28 is provided on the pipeline connecting the radioactive waste sodium reactor 15 and the steam-water separator 29 .
[0086] Furthermore, the exhaust gas filtering mechanism includes two exhaust gas filters A42 and B45 connected in parallel.
[0087] Furthermore, an isolation valve A39 is arranged on the pipeline connecting the exhaust gas filtering mechanism and the radioactive waste sodium reactor 15, an isolation valve B40 is arranged on the pipeline connecting the exhaust gas filtering mechanism and the steam-water separator 29, an exhaust gas filter A inlet isolation valve 41 is arranged at the inlet of the exhaust gas filter A42, an exhaust gas filter A outlet isolation valve 43 is arranged at the outlet of the exhaust gas filter A42, an exhaust gas filter B inlet isolation valve 44 is arranged at the inlet of the exhaust gas filter B45, an exhaust gas filter B outlet isolation valve 46 is arranged at the outlet of the exhaust gas filter B45, an exhaust gas filter B outlet isolation valve 48 is arranged at the outlet of the exhaust gas exhaust fan 47, an isolation valve C50 is arranged between the inlet of the exhaust gas filtering mechanism and the exhaust gas exhaust fan outlet isolation valve 48 through a pipeline, the exhaust gas exhaust fan outlet isolation valve 48 is connected to the ventilation system of the plant where the system is located through a pipeline, and a radioactive measuring instrument 51 and an exhaust gas exhaust valve 49 are arranged in sequence on the pipeline connecting the exhaust gas exhaust fan outlet isolation valve 48 and the ventilation system of the plant where the system is located.
[0088] Furthermore, a cooling water inlet valve 37 is provided at the inlet of the cooling water system, a cooling water outlet valve 38 is provided at the outlet of the cooling water system, and the cooling water side of the steam-water separator 29 is connected to the cooling water inlet valve 37 and the cooling water outlet valve 38 through pipelines.
[0089] Furthermore, a waste liquid discharge valve 31 is arranged on the pipeline connecting the radioactive waste sodium reactor 15 and the waste liquid discharge pump 32, a waste liquid discharge pump outlet valve 33 is arranged at the outlet of the waste liquid discharge pump 32, a steam-water separator outlet valve 30 is arranged on the condensate side connected to the steam-water separator 29, a waste liquid collection tank inlet isolation valve 34 is arranged at the inlet of the waste liquid collection tank, and the waste liquid discharge pump outlet valve 33 and the steam-water separator outlet valve 30 are both connected to the waste liquid collection tank inlet isolation valve 34 through pipelines.
[0090] All valves connected to the radioactive waste sodium treatment system are initially set to the closed state.
[0091] The radioactive waste sodium generated during the maintenance of radioactive sodium-related equipment and during the sampling and analysis of the primary circuit is stored in the radioactive waste sodium temporary storage container 1.
[0092] During daily temporary storage, the argon storage tank outlet isolation valve 9 and the waste sodium temporary storage container argon inlet isolation valve 10 are opened to introduce argon into the radioactive waste sodium temporary storage container 1 for protection.
[0093] When radioactive waste sodium needs to be treated, the following steps are included:
[0094] 1. Evacuate the radioactive sodium waste reactor 15, open the isolation valve A39, the inlet isolation valve 41 of the waste gas filter A, the outlet isolation valve 43 of the waste gas filter A, the outlet isolation valve 48 of the waste gas exhaust fan and the waste gas exhaust valve 49, start the waste gas exhaust fan 47, evacuate the radioactive sodium waste reactor 15, reduce the oxygen content in the radioactive sodium waste reactor 15, and when the pressure gauge D24 measures a slight negative pressure (less than 0 MPa) in the radioactive sodium waste reactor 15, stop the waste gas exhaust fan 47, and close the isolation valve A39, the inlet isolation valve 41 of the waste gas filter A, the outlet isolation valve 43 of the waste gas filter A, the outlet isolation valve 48 of the waste gas exhaust fan and the waste gas exhaust valve 49.
[0095] 2. Pre-treatment of radioactive waste sodium: closing the argon inlet isolation valve 10 of the waste sodium temporary storage container, starting the radioactive waste sodium heating device 7 and the radioactive waste sodium transportation pipeline heating device; when the temperature of the radioactive waste sodium heating device 7 reaches 120 degrees Celsius, the radioactive waste sodium heating device 7 is automatically powered off; when the temperature of the radioactive waste sodium heating device 7 is lower than 110 degrees Celsius, the radioactive waste sodium heating device 7 is automatically powered on for heating; when the temperature of the radioactive waste sodium transportation pipeline heating device reaches 120 degrees Celsius, the radioactive waste sodium transportation pipeline heating device is automatically powered off; when the temperature of the radioactive waste sodium transportation pipeline heating device is lower than 110 degrees Celsius, the radioactive waste sodium transportation pipeline heating device is automatically powered on for heating.
[0096] 3. Radioactive waste sodium transportation: opening the isolation valve 2 before the radioactive waste sodium filter, the isolation valve 4 after the radioactive waste sodium filter, and the inlet valve 6 of the radioactive waste sodium reactor, starting the radioactive waste sodium transportation pump 5, after the liquid radioactive waste sodium is filtered through the radioactive waste sodium filter 3 to remove impurities, the radioactive waste sodium is atomized and sprayed onto the partition of the radioactive waste sodium reactor 15 through the radioactive waste sodium injection device 14, when the injection metering of the radioactive waste sodium injection device 14 reaches the set value (500 grams), the radioactive waste sodium transportation pump 5 automatically stops, and the isolation valve 2 before the radioactive waste sodium filter, the isolation valve 4 after the radioactive waste sodium filter, and the inlet valve 6 of the radioactive waste sodium reactor are closed, and the transportation of the radioactive waste sodium is completed.
[0097] 4. Radioactive waste sodium reaction control: slowly open the water vapor inlet isolation valve A21 and the water vapor inlet isolation valve B53, and the water vapor system introduces water vapor into the radioactive waste sodium reactor 15. The water vapor in the radioactive waste sodium reactor 15 reacts with the radioactive sodium to generate sodium hydroxide solution and hydrogen.
[0098] During the reaction process, the reaction rate of water vapor and radioactive waste sodium is controlled by controlling the flow rate of water vapor added to the radioactive waste sodium reactor 15. The system measures the pressure, temperature and hydrogen content in the radioactive waste sodium reactor 15 in real time through the pressure gauge D24, the thermometer 25 and the hydrogen meter 26, and sets limits for the pressure, temperature and hydrogen content in the radioactive waste sodium reactor 15. When the measured values exceed the set limits, the water vapor inlet isolation valve A21 and the water vapor inlet isolation valve B53 are automatically closed through the automatic control interlock, the water vapor supply is stopped, and the reaction rate of water vapor and radioactive waste sodium in the radioactive reactor 15 is slowed down.
[0099] As the reaction time continues, the concentration of the generated hydrogen increases. When the hydrogen solubility in the radioactive sodium waste reactor 15 reaches 2.5%, the system automatically closes the water vapor inlet isolation valve A 21 and the water vapor inlet isolation valve B 53, and the water vapor in the radioactive sodium waste reactor 15 continues to react with the radioactive sodium waste; when the hydrogen solubility in the radioactive sodium waste reactor 15 reaches 3.0%, the system automatically opens the nitrogen storage tank outlet isolation valve 18 and the radioactive sodium waste reactor gas inlet isolation valve 20, and the nitrogen storage tank 16 introduces nitrogen into the radioactive sodium waste reactor 15 to prevent the hydrogen solubility in the radioactive sodium waste reactor 15 from being greater than or equal to 4%, causing an explosion; when the hydrogen solubility in the radioactive sodium waste reactor 15 drops to less than 1%, the system automatically closes the nitrogen storage tank outlet isolation valve 18 and the radioactive sodium waste reactor gas inlet isolation valve 20, and then automatically opens the water vapor inlet isolation valve A 21 and the water vapor inlet isolation valve B 53, the water vapor system slowly introduces water vapor into the radioactive waste sodium reactor 15; the control is continued according to the above requirements, and the above steps are repeated for multiple times until the hydrogen solubility in the radioactive waste sodium reactor 15 no longer increases, indicating that the radioactive waste sodium in the radioactive waste sodium reactor 15 has reacted completely. At this time, the system automatically closes the nitrogen storage tank outlet isolation valve 18, the radioactive waste sodium reactor gas inlet isolation valve 20, the water vapor inlet isolation valve A 21, and the water vapor inlet isolation valve B 53.
[0100] During the reaction, if the pressure in the radioactive sodium waste reactor 15 reaches 1.5 MPa (the reactor design pressure is 2 MPa), it also indicates that the radioactive sodium waste in the radioactive sodium waste reactor 15 has been completely reacted. At this time, the system automatically closes the nitrogen storage tank outlet isolation valve 18, the radioactive sodium waste reactor gas inlet isolation valve 20, the water vapor inlet isolation valve A 21, and the water vapor inlet isolation valve B 53.
[0101] 5. Radioactive waste gas monitoring and emission
[0102] When the exhaust filter A 42 is in normal use, the system automatically opens the gas discharge outlet valve 28, the steam-water separator outlet valve 30, the waste liquid collection tank inlet isolation valve 34, the cooling water inlet valve 37, the cooling water outlet valve 38, the isolation valve B 40, the exhaust filter A inlet isolation valve 41, the exhaust filter A outlet isolation valve 43, the exhaust gas discharge fan outlet isolation valve 48 and the exhaust gas discharge valve 49, and automatically starts the exhaust gas discharge fan 47. After the radioactive waste gas after the reaction is separated into gas and liquid by the steam-water separator 29, the gas is filtered by the exhaust filter A42, and the radioactivity measuring instrument 51 detects that the gas is qualified before it is discharged into the ventilation system of the plant where the system is located; after the gas is filtered by the exhaust filter A42 and the radioactivity measuring instrument 51 detects that the gas is unqualified, the system automatically closes the exhaust gas discharge valve 49, automatically opens the isolation valve C50, and circulates through the exhaust filter A42 until the radioactivity measuring instrument 51 detects that the gas is qualified before it is discharged into the ventilation system of the plant where the system is located. When the pressure gauge D24 shows less than 0MPa, the system automatically stops the exhaust gas exhaust fan 47, and automatically closes the gas exhaust outlet valve 28, the steam-water separator outlet valve 30, the waste liquid collection tank inlet isolation valve 34, the cooling water inlet valve 37, the cooling water outlet valve 38, the isolation valve B 40, the exhaust gas filter A inlet isolation valve 41, the exhaust gas filter A outlet isolation valve 43, the exhaust gas exhaust fan outlet isolation valve 48 and the exhaust gas exhaust valve 49.
[0103] When the exhaust filter A 42 fails or fails, the system automatically opens the gas discharge outlet valve 28, the steam-water separator outlet valve 30, the waste liquid collection tank inlet isolation valve 34, the cooling water inlet valve 37, the cooling water outlet valve 38, the isolation valve B 40, the exhaust filter B inlet isolation valve 44, the exhaust filter B outlet isolation valve 46, the exhaust gas discharge fan outlet isolation valve 48 and the exhaust gas discharge valve 49, and automatically starts the exhaust gas discharge fan 47. After the radioactive waste gas after the reaction is separated into gas and liquid by the steam-water separator 29, the gas is filtered by the exhaust filter A42, and the radioactivity measuring instrument 51 detects that the gas is qualified before it is discharged into the ventilation system of the plant where the system is located; after the gas is filtered by the exhaust filter A42 and the radioactivity measuring instrument 51 detects that the gas is unqualified, the system automatically closes the exhaust valve 49, automatically opens the isolation valve C50, and circulates through the exhaust filter A42 until the radioactivity measuring instrument 51 detects that the gas is qualified before it is discharged into the ventilation system of the plant where the system is located. When the pressure gauge D24 shows less than 0MPa, the system automatically stops the exhaust gas exhaust fan 47, and automatically closes the gas exhaust outlet valve 28, the steam-water separator outlet valve 30, the waste liquid collection tank inlet isolation valve 34, the cooling water inlet valve 37, the cooling water outlet valve 38, the isolation valve B 40, the exhaust gas filter B inlet isolation valve 44, the exhaust gas filter B outlet isolation valve 46, the exhaust gas exhaust fan outlet isolation valve 48 and the exhaust gas exhaust valve 49.
[0104] 6. The radioactive sodium waste reactor 15 is flushed, and the system automatically opens the deionized water inlet valve 22. The deionized water system injects deionized water into the radioactive sodium waste reactor 15. The system measures the liquid level in the radioactive sodium waste reactor 15 in real time through the liquid level gauge 27, and sets a limit value for the liquid level in the radioactive sodium waste reactor 15. When the measured value exceeds the set limit value, the system automatically closes the deionized water inlet valve 22. If the values of the pressure gauge 24D and the hydrogen meter 26 do not change within the set time (5 minutes), the system continues to automatically open the deionized water inlet valve 22, and the deionized water system injects deionized water into the radioactive sodium waste reactor 15. The above operation is repeated until the liquid level in the radioactive sodium waste reactor 15 reaches the total set value, and the system automatically closes the deionized water inlet valve 22.
[0105] The outlet isolation valve 9 of the argon storage tank and the argon inlet isolation valve 11 of the radioactive waste sodium reactor are opened, and argon is introduced into the radioactive waste sodium reactor 15 for protection.
[0106] 7. Radioactive waste liquid monitoring and discharge, the system automatically opens the waste liquid discharge valve 31, the waste liquid discharge pump outlet valve 33, and the waste liquid collection tank inlet isolation valve 34, automatically starts the waste liquid discharge pump 32, and discharges the reacted radioactive waste liquid into the waste liquid collection tank 35. The system then automatically closes the waste liquid discharge valve 31, the waste liquid discharge pump outlet valve 33, and the waste liquid collection tank inlet isolation valve 34, and automatically stops the waste liquid discharge pump 32. When the liquid level in the waste liquid collection tank 35 reaches the set value, the system automatically opens the waste liquid collection tank outlet isolation valve 36, and after discharging the radioactive waste liquid into the power station radioactive waste liquid treatment system, the system automatically closes the waste liquid collection tank outlet isolation valve 36.
[0107] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.
Claims
1. A radioactive waste sodium treatment system, It is characterized in that It includes a radioactive waste sodium pretreatment unit, a radioactive waste sodium treatment unit, a radioactive waste gas treatment unit and a radioactive waste liquid treatment unit; The radioactive waste sodium pretreatment unit is connected to the radioactive waste sodium treatment unit through a pipeline, and the radioactive waste sodium treatment unit is respectively connected to the radioactive waste gas treatment unit and the radioactive waste liquid treatment unit through pipelines; The radioactive waste sodium pretreatment unit converts the radioactive waste sodium to be treated from solid to liquid, and then filters and transports it to the radioactive waste sodium treatment unit; The radioactive waste sodium treatment unit adopts a water vapor + nitrogen treatment process, controls the reaction rate with radioactive waste sodium by controlling the water vapor, controls the injection amount of water vapor and nitrogen by detecting the concentration of hydrogen in the reactor to control the rate of sodium-water reaction, and the radioactive waste liquid after the reaction is transported to the radioactive waste liquid treatment unit; after the radioactive waste gas after the reaction is separated into gas and liquid, the gas is transported to the radioactive waste gas treatment unit, and the liquid is transported to the radioactive waste liquid treatment unit; The radioactive liquid waste treatment unit stores the radioactive liquid waste to a certain liquid level and then discharges it into the radioactive liquid waste treatment system of the power station; The radioactive waste gas treatment unit circulates and filters the radioactive waste gas until it meets the radioactive waste gas emission standards and then discharges it into the ventilation system of the plant where the system is located; The radioactive waste sodium pretreatment unit comprises a radioactive waste sodium temporary storage container, a radioactive waste sodium filter, a radioactive waste sodium delivery pump and a radioactive waste sodium barrel heating device; The radioactive waste sodium treatment unit comprises a radioactive waste sodium injection device, a radioactive waste sodium reactor, a desalted water system, a water vapor system and a mixed gas system; The radioactive liquid waste treatment unit comprises a waste liquid discharge pump and a waste liquid collection tank; The radioactive waste gas treatment unit includes a waste gas filtering mechanism, a waste gas exhaust fan and a radioactivity measuring instrument; The radioactive sodium waste temporary storage container is placed on the radioactive sodium waste barrel heating device; The radioactive sodium waste temporary storage container is connected to the radioactive sodium waste filter, the radioactive sodium waste delivery pump and the radioactive sodium waste injection device in sequence through pipelines; The radioactive sodium waste spraying device is suspended in the radioactive sodium waste reactor; three layers of partitions with different apertures are arranged in the radioactive sodium waste reactor, and the radioactive sodium waste spraying device sprays radioactive liquid sodium onto the partitions with different apertures in the radioactive sodium waste reactor; The upper part of the radioactive sodium waste reactor is connected to the inlet of the exhaust gas filtration mechanism and the desalted water system through pipelines, the middle part of the radioactive sodium waste reactor is connected to the water vapor system and the mixed gas system through pipelines, and the bottom of the radioactive sodium waste reactor is connected to the waste liquid discharge pump and the waste liquid collection tank in sequence through pipelines; The outlet of the exhaust gas filtering mechanism is connected to the exhaust gas exhaust fan and the radioactivity measuring instrument in sequence through pipelines.
2. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The radioactive waste sodium treatment unit also includes a steam-water separator and a cooling water system. The upper side of the radioactive waste sodium reactor is connected to the steam-water separator through a pipeline, the condensate side of the steam-water separator is connected to the waste liquid collection tank through a pipeline, the cooling water side of the steam-water separator is connected to the cooling water system through a pipeline, and the gas side of the steam-water separator is connected to the inlet of the exhaust gas filtering mechanism through a pipeline.
3. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The radioactive sodium waste pretreatment unit also includes a radioactive sodium waste delivery pipeline heating device for heating pipelines connecting the radioactive sodium waste temporary storage container, the radioactive sodium waste delivery pump, and the radioactive sodium waste injection device.
4. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The radioactive waste sodium pretreatment unit also includes an argon storage tank, which is connected to the radioactive waste sodium temporary storage container and the radioactive waste sodium reactor through pipelines.
5. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The radioactive waste sodium processing unit also includes a pressure gauge D, a thermometer, a hydrogen meter and a liquid level gauge, and the pressure gauge D, the thermometer, the hydrogen meter and the liquid level gauge are respectively installed on the top of the radioactive waste sodium reactor through pipelines.
6. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The exhaust gas filtering mechanism comprises two exhaust gas filters A and B which are connected in parallel.
7. The radioactive waste sodium treatment system according to claim 1, It is characterized in that The radioactive waste sodium treatment system uses electric valves as valves, and is automatically controlled by PLC. The PLC control uses Siemens S7.0 version to program the electric valves in the system to achieve automatic operation and control of the system.
8. A method for treating radioactive waste sodium, It is characterized in that The radioactive sodium waste treatment system according to any one of claims 1 to 7 comprises the following steps: converting the radioactive sodium waste to be treated from a solid state to a liquid state, filtering and reacting with water vapor; during the reaction, controlling the reaction rate of the radioactive sodium waste and the water vapor; after the radioactive waste gas after the reaction is separated from the gas and liquid, the gas is circulated and filtered to meet the radioactive waste gas emission standards and then discharged to the ventilation system of the plant where the system is located, and the liquid and the radioactive waste liquid after the reaction are stored to a certain liquid level and then discharged into the radioactive waste liquid treatment system of the power station.
