CN115295199A - Hydrogen-containing radioactive waste gas treatment system and method for nuclear power plant - Google Patents
Hydrogen-containing radioactive waste gas treatment system and method for nuclear power plant Download PDFInfo
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- CN115295199A CN115295199A CN202210783308.2A CN202210783308A CN115295199A CN 115295199 A CN115295199 A CN 115295199A CN 202210783308 A CN202210783308 A CN 202210783308A CN 115295199 A CN115295199 A CN 115295199A
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Abstract
The invention relates to a system and a method for treating hydrogen-containing radioactive waste gas of a nuclear power plant, wherein the system comprises a pretreatment unit, a treatment loop and a filtering and discharging unit; the processing loop comprises a retention processing unit, a monitoring unit and a gas recovery unit; after the pressure of the hydrogen-containing radioactive waste gas is regulated and dried by the pretreatment unit, the hydrogen-containing radioactive waste gas enters a treatment loop for decay and monitoring, and is discharged to the external environment through the filtering and discharging unit; the method is applicable to the system and comprises the steps of obtaining a monitoring result of a monitoring unit, switching to a first filtering branch or a second filtering branch according to the monitoring result to filter waste gas, and controlling to switch on or switch off a gas recovery unit; wherein the monitoring result comprises the concentration of the activity of the hydrogen-containing radioactive off-gas. The invention continuously monitors the activity concentration of the hydrogen-containing waste gas in an online monitoring mode, realizes the continuous monitoring of waste gas emission, the management and the control automation of waste gas emission, realizes the automatic switching of the discharge branch of the iodine filter and improves the operation safety of the nuclear power plant.
Description
Technical Field
The invention relates to the technical field of waste gas treatment of nuclear power plants, in particular to a system and a method for treating hydrogen-containing radioactive waste gas of a nuclear power plant.
Background
Nuclear power plant pressure vessels (reactor cores) store a large number of nuclear fuel rods for nuclear reactions. During the power operation of the nuclear power plant, neutrons in the core react with contaminated uranium on the surface of the fuel rods and chain fission of the uranium in the fuel rods to generate a large amount of radioactive inert gases and iodine, mainly krypton isotopes (Kr-83 m, kr-85, kr-87 and Kr-88), xenon isotopes (Xe-131 m, xe-133m, xe-135 and Xe-138) and iodine isotopes (I-131, I-132, I-133, I-134 and I-135), which enter the main loop of the nuclear power plant and its auxiliary systems along with migration of the coolant of the main loop. In order to ensure that the concentration of the activity of the inert gas of the coolant of the main loop is lower than the technical specification limit of the nuclear power plant radiochemistry, and the radioactivity level of the inert gas released in the process of stopping the nuclear power plant and opening the large cover of the pressure container is maintained within a reasonable range, hydrogen is adopted to purge the main loop during the power operation of the power plant, and the inert gas nuclide and the gas-borne iodine are purged to a radioactive waste gas treatment system of the nuclear power plant from the main loop.
The radioactive waste gas treatment system is mainly used for treating radioactive hydrogen-containing waste gas and oxygen-containing waste gas generated in the normal operation period of the nuclear power plant, the radioactive hydrogen-containing waste gas is discharged to a ventilation system of a factory building and is discharged to the atmosphere after being stored and decayed by a storage tank or being retained and decayed by an active carbon retention bed, and the oxygen-containing waste gas is discharged to the atmosphere by the ventilation system of the factory building after being filtered and diluted by iodine. At present, a radioactive waste gas treatment system of a nuclear power plant adopts a storage tank or an active carbon retention bed to collect hydrogen-containing radioactive waste gas generated by the nuclear power plant. The hydrogen-containing radioactive waste gas is collected in a storage tank or a detention bed by a compressor under pressure, and the radioactive activity concentration of the waste gas is continuously reduced by utilizing the self-decay of radioactive inert gas nuclide (such as krypton and xenon isotopes) and radioactive iodine in the waste gas. In the prior art, sampling and analysis of the radioactive activity concentration of iodine in gas are required before exhaust gas is discharged, and the radiation chemical analysis personnel of a power plant have higher irradiation dose and workload; the wrong information transmission between a sampling analysis engineer and an exhaust gas treatment engineer or the wrong operation of the exhaust gas treatment engineer can lead the storage time of the exhaust gas in the storage tank to be less than 60 days, thus the risk is discharged by mistake; in addition, in the exhaust emission process, workers need to continuously pay attention to pressure changes in the storage tanks on site, before each tank is exhausted, the exhaust of the ventilation system is manually switched to an exhaust loop of the iodine filter, the replacement frequency of the iodine filter and the amount of radioactive solid waste in a power plant are increased, and the site radiation risk of the workers is high.
Disclosure of Invention
The technical problem to be solved by the present invention is to provide a safe and automatic monitoring and control system and method for treating hydrogen-containing radioactive waste gas from a nuclear power plant, aiming at least one of the defects of the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: constructing a hydrogen-containing radioactive waste gas treatment system of a nuclear power plant, which is characterized by comprising a pretreatment unit, a treatment loop and a filtering and discharging unit; the treatment loop comprises a retention treatment unit, a monitoring unit and a gas recovery unit, wherein an inlet of the pretreatment unit is connected with the main loop of the nuclear power plant, an outlet of the pretreatment unit is connected with an inlet of the retention treatment unit, and an outlet of the retention treatment unit is connected with an inlet of the monitoring unit; one path of an outlet of the monitoring unit is connected with an inlet of the gas recovery unit, and the other path of the outlet of the monitoring unit is connected with an inlet of the filtering and discharging unit; the outlet of the gas recovery unit is connected with the inlet of the retention treatment unit; the filtering and discharging unit comprises a first filtering branch and a second filtering branch which are arranged in parallel, and an outlet of the filtering and discharging unit is communicated with the external environment;
the hydrogen-containing radioactive waste gas of the nuclear power plant enters the treatment loop for decay and monitoring after the pretreatment unit is used for pressure regulation and drying, and the hydrogen-containing radioactive waste gas passes through the filtering and discharging unit and is discharged into the external environment.
Preferably, the pretreatment unit comprises a compressor and a dryer, and the hydrogen-containing radioactive waste gas of the nuclear power plant is pressurized by the compressor and then discharged to the dryer for drying treatment.
Preferably, the pretreatment unit further comprises a buffer tank, wherein a first end of the buffer tank is connected with the main loop of the nuclear power plant, and a second end of the buffer tank is connected with a first end of the compressor and is used for collecting the radioactive waste gas containing hydrogen generated by the main loop of the nuclear power plant.
Preferably, the pretreatment unit further comprises a gas cooler, wherein a first end of the gas cooler is connected with the second end of the compressor, and a second end of the gas cooler is connected with the first end of the dryer.
Preferably, the dryer is a silica gel dryer.
Preferably, the retention treatment unit comprises at least one retention bed of activated carbon, at least one of the retention beds of activated carbon being connected to the outlet of the pretreatment unit.
Preferably, the number of the activated carbon retention beds is two, and the activated carbon retention beds comprise a first activated carbon retention bed and a second activated carbon retention bed; and waste gas at the outlet of the pretreatment unit sequentially passes through the first activated carbon retention bed and the second activated carbon retention bed for retention decay.
Preferably, the hydrogen-containing radioactive waste gas treatment system of the nuclear power plant is further provided with a pressure regulating valve for regulating the pressure of the hydrogen-containing radioactive waste gas of the nuclear power plant; the pressure regulating valve is disposed between the pretreatment unit and the retention treatment unit.
Preferably, the monitoring unit includes at least one monitoring device that is used for monitoring the waste gas of the exit of processing unit is detained, monitoring device first end with the exit of detaining processing unit links to each other, monitoring device second end all the way with the entry linkage of gas recovery unit, its another way with the entry of filtering discharge unit links to each other.
Preferably, the number of the monitoring devices is one, and the gas recovery unit comprises a seventh isolation valve, a circulation pump and a ninth isolation valve;
the outlet of the retention treatment unit is connected with the first end of the monitoring device through a first isolation valve, one path of the second end of the monitoring device is connected to the inlet of the retention treatment unit through the seventh isolation valve, the circulating pump and the ninth isolation valve in sequence, and the other path of the second end of the monitoring device is connected to the inlet of the filtering and discharging unit through a third isolation valve.
Preferably, the number of the monitoring devices is two, and the monitoring devices comprise a first monitoring device and a second monitoring device which are arranged in parallel; the gas recovery unit comprises a seventh isolation valve, an eighth isolation valve, a circulating pump and a ninth isolation valve;
one path of an outlet of the detention processing unit is connected with a first end of the first monitoring device through a first isolation valve, and the other path of the outlet of the detention processing unit is connected with a first end of the second monitoring device through a second isolation valve;
one path of the second end of the first monitoring device is connected to the inlet of the retention treatment unit through the seventh isolation valve, the circulating pump and the ninth isolation valve in sequence, and the other path of the second end of the first monitoring device is connected to the inlet of the filtration and discharge unit through the third isolation valve; one path of the second end of the second monitoring device is connected to the inlet of the retention treatment unit sequentially through the eighth isolation valve, the circulating pump and the ninth isolation valve, and the other path of the second end of the second monitoring device is connected to the inlet of the filtering and discharging unit through a fourth isolation valve.
Preferably, the filtering and discharging unit further comprises an exhaust device for discharging exhaust gas, and the exhaust gas filtered by the first filtering branch or the second filtering branch is discharged to the external environment through the exhaust device.
Preferably, the first filtering branch comprises a fifth isolation valve and an aerosol filter, and one path of the outlet of the monitoring unit is connected to the exhaust device through the fifth isolation valve and the aerosol filter in sequence.
Preferably, the second filtering branch comprises a sixth isolating valve and an iodine filter, and one path of the outlet of the monitoring unit is connected to the exhaust device sequentially through the sixth isolating valve and the iodine filter.
Preferably, the system for treating the hydrogen-containing radioactive waste gas of the nuclear power plant further comprises a gas monitor, wherein the gas monitor is arranged on the exhaust device and used for monitoring the waste gas in the exhaust device.
Preferably, the filtering and discharging unit further comprises a ventilation device, the ventilation device is arranged on a pipeline between the monitoring unit and the filtering and discharging unit, and exhaust of the ventilation device is used for diluting exhaust gas which is monitored by the monitoring unit and then discharged to the first filtering branch or the second filtering branch.
The invention also constructs a method for treating the hydrogen-containing radioactive waste gas of the nuclear power plant, which is suitable for the hydrogen-containing radioactive waste gas treatment system of the nuclear power plant, and comprises the following steps:
s1, acquiring a monitoring result of the monitoring unit, switching to the first filtering branch or the second filtering branch according to the monitoring result to filter waste gas, and controlling to switch on or switch off the gas recovery unit; wherein the monitoring result comprises the radioactivity concentration of the hydrogen-containing radioactive waste gas.
Preferably, the step S1 specifically includes:
s11, judging whether the monitoring results are all larger than a first threshold value within a first preset time, if so, executing a step S12, and if not, switching to the first filtering branch for waste gas filtering;
s12, switching to the second filtering branch for filtering the waste gas, and continuously judging whether the monitoring result is greater than a second threshold value within second preset time, if so, executing a step S13, and if not, executing a step S11; wherein the second threshold is greater than the first threshold;
and S13, stopping discharging the waste gas to the filtering and discharging unit, and automatically triggering and connecting the gas recovery unit to perform waste gas circulation treatment.
The implementation of the invention has the following beneficial effects: the invention continuously monitors the activity concentration of the hydrogen-containing waste gas in an online monitoring mode, realizes the continuous monitoring of waste gas emission, the management and the control automation of waste gas emission, reduces the error emission of radioactive waste gas due to insufficient decay caused by human error, reduces the workload and the irradiated dose of radiochemistry workers, realizes the automatic switching of an iodine filter emission branch and improves the operation safety of a nuclear power plant.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic diagram of a nuclear power plant hydrogen-containing radioactive waste gas treatment system according to the present invention;
FIG. 2 is a control logic diagram of one embodiment of a method of treating hydrogen-containing radioactive waste gas from a nuclear power plant in accordance with the present invention;
FIG. 3 is a control logic diagram of another embodiment of the method for treating hydrogen-containing radioactive waste gas from a nuclear power plant of the present invention;
FIG. 4 is a control logic diagram of one embodiment of the monitoring unit of the present invention;
FIG. 5 is a control logic diagram of another embodiment of a monitoring unit of the present invention;
fig. 6 is a block flow diagram of a method for treating hydrogen-containing radioactive waste gas from a nuclear power plant according to the present invention.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings. In the following description, it is to be understood that the orientations and positional relationships indicated by "front", "rear", "upper", "lower", "left", "right", "longitudinal", "lateral", "vertical", "horizontal", "top", "bottom", "inner", "outer", "leading", "trailing", and the like are configured and operated in specific orientations based on the orientations and positional relationships shown in the drawings, and are only for convenience of describing the present invention, and do not indicate that the device or element referred to must have a specific orientation, and thus, are not to be construed as limiting the present invention.
It is also noted that, unless expressly stated or limited otherwise, the terms "mounted," "connected," "secured," "disposed," and the like are intended to be inclusive and mean, for example, that they may be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; either directly or indirectly through intervening media, either internally or in any other relationship. When an element is referred to as being "on" or "under" another element, it can be "directly" or "indirectly" on the other element or intervening elements may also be present. The terms "first", "second", "third", etc. are merely for convenience in describing the present technical solution and are not to be construed as indicating or implying any relative importance or implicitly indicating the number of technical features indicated, whereby the features defined as "first", "second", "third", etc. may explicitly or implicitly include one or more of such features. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the following description, for purposes of explanation and not limitation, specific details are set forth such as particular system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the invention. It will be apparent, however, to one skilled in the art that the present invention may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.
As shown in fig. 1, the system for treating hydrogen-containing radioactive waste gas from a nuclear power plant according to the present invention comprises a pretreatment unit 1, a treatment loop 2 and a filtering and discharging unit 3;
the treatment loop 2 comprises a retention treatment unit 21, a monitoring unit 22 and a gas recovery unit 23, wherein an inlet of the pretreatment unit 1 is connected with a main loop 100 of the nuclear power plant, an outlet of the pretreatment unit 1 is connected with an inlet of the retention treatment unit 21, and an outlet of the retention treatment unit 21 is connected with an inlet of the monitoring unit 22; the outlet of the monitoring unit 22 is divided into two branches, one branch is connected with the inlet of the gas recovery unit 23, the other branch is connected with the inlet of the filtering and discharging unit 3, and the gas recovery unit 23 is isolated from the monitoring unit 22 in the general initial state; the outlet of the gas recovery unit 23 is connected to the inlet of the retention treatment unit 21; the filtering and discharging unit 3 comprises a first filtering branch 31 and a second filtering branch 32 which are arranged in parallel, and the outlet of the filtering and discharging unit 3 is communicated with the external environment; after the hydrogen-containing radioactive waste gas of the nuclear power plant is subjected to pressure regulation and drying by the pretreatment unit 1, the hydrogen-containing radioactive waste gas enters the treatment loop 2 for decay and monitoring, and is discharged into the external environment through the filtering and discharging unit 3.
In order to ensure the adsorption capacity of the activated carbon particles in the retention treatment unit 21, the hydrogen-containing waste gas from the nuclear power plant needs to be subjected to pressure regulation and drying treatment by the pretreatment unit 1 before entering the retention treatment unit 21. Further, the pretreatment unit 1 comprises a compressor 12 and a dryer 14, wherein the dryer 14 is mainly used for dehumidifying the hydrogen-containing waste gas of the nuclear power plant, and particularly, the silica gel dryer 14 can be selected; the hydrogen-containing radioactive waste gas of the nuclear power plant is pressurized by a compressor 12 and then discharged to a dryer 14 for drying treatment.
In some embodiments, the pretreatment unit 1 further comprises a buffer tank 11 for collecting the hydrogen-containing radioactive waste gas generated by the primary circuit 100 of the nuclear power plant, a first end of the buffer tank 11 is connected to the primary circuit 100 of the nuclear power plant, and a second end of the buffer tank 11 is connected to a first end of the compressor 12; the hydrogen-containing radioactive waste gas generated by the primary loop 100 of the nuclear power plant is collected in the buffer tank 11, pressurized by the compressor 12 and then discharged to the dryer 14 for drying treatment.
In other embodiments, the pretreatment unit 1 further comprises a gas cooler 13, a first end of the gas cooler 13 is connected with a second end of the compressor 12, and a second end of the gas cooler 13 is connected with a first end of the dryer 14; after being pressurized by the compressor 12, the hydrogen-containing radioactive waste gas of the nuclear power plant is discharged to the gas cooler 13 for cooling treatment, and then is dried by the dryer 14, so that a large amount of water in the hydrogen-containing radioactive waste gas is removed. The buffer tank 11 collects hydrogen-containing radioactive waste gas of a nuclear power plant, the hydrogen-containing radioactive waste gas is discharged to the gas cooler 13 and the silica gel dryer 14 through the compressor 12 for pretreatment, the pretreated hydrogen-containing waste gas is retained and decayed for a long time through the retention treatment unit 21, the radioactive nuclide in the discharged waste gas is only Kr-85, the gamma ray yield is 0.43%, and the beta ray yield is 99.57%.
Further, the retention treatment unit 21 comprises at least one activated carbon retention bed, the at least one activated carbon retention bed is connected with the outlet of the pretreatment unit 1, and the radioactive inert gases krypton and xenon in the hydrogen-containing waste gas of the nuclear power plant are adsorbed by using activated carbon particles in the activated carbon retention bed.
In some embodiments, in order to achieve a better adsorption effect, the number of the disposed activated carbon retentate beds may be two, which includes the first activated carbon retentate bed 211 and the second activated carbon retentate bed 212; the waste gas at the outlet of the pretreatment unit 1 passes through a first activated carbon retention bed 211 and a second activated carbon retention bed 212 in turn for retention decay. Further, after the retention and decay of the retention treatment unit 21, the waste gas can be filtered by arranging a filter 17, and the filter 17 is used for filtering small activated carbon particles mixed in the gas at the outlet of the activated carbon retention bed, so that the downstream gas is ensured to be clean and free of activated carbon particle impurities.
Furthermore, the system for treating the hydrogen-containing radioactive waste gas of the nuclear power plant is also provided with a pressure regulating valve for regulating the pressure of the hydrogen-containing radioactive waste gas of the nuclear power plant; the pressure regulating valve is arranged between the pretreatment unit 1 and the residence treatment unit 21, i.e. the outlet of the pretreatment unit 1 is connected to the inlet of the residence treatment unit 21 by the pressure regulating valve. In some embodiments, the number of the pressure regulating valves is two, and the pressure regulating valves include a first pressure regulating valve 15 and a second pressure regulating valve 16, and the outlet of the pretreatment unit 1 is connected to the first pressure regulating valve 15 and the second pressure regulating valve 16 in turn, and is connected to the inlet of the stagnation treatment unit 21; an outlet of the gas recovery unit 23 is connected to a pipe between the first pressure regulating valve 15 and the second pressure regulating valve 16.
Further, the monitoring unit 22 comprises at least one monitoring device for monitoring the exhaust gas at the outlet of the retention treatment unit 21, and a first end of the monitoring device is connected with the outlet of the retention treatment unit 21 and is used for monitoring the exhaust gas treated by the retention treatment unit 21, and specifically measuring the radioactivity concentration of the exhaust gas discharged at the outlet of the retention treatment unit 21; the monitoring devices second end is connected with the entry of gas recovery unit 23 all the way, and its another way links to each other with the entry of filtering emission unit 3, if through the qualified waste gas of monitoring devices monitoring, can discharge through filtering emission unit 3, if through the unqualified waste gas of monitoring devices monitoring, will get into gas recovery unit 23 and carry out the circulation and retreatment.
Specifically, in some embodiments, the number of the monitoring devices may be one, and the gas recovery unit 23 includes a seventh isolation valve 47, a circulation pump, and a ninth isolation valve 49; the outlet of the retention treatment unit 21 is connected with the first end of a monitoring device through a first isolation valve 41, one path of the second end of the monitoring device is connected to the inlet of the retention treatment unit 21 through a seventh isolation valve 47, a circulating pump and a ninth isolation valve 49 in sequence, and the other path of the second end of the monitoring device is connected to the inlet of the filtration and discharge unit 3 through a third isolation valve 43; if qualified waste gas is monitored by the monitoring device, the system automatically opens the third isolating valve 43, and the waste gas is discharged through the filtering and discharging unit 3; if unqualified waste gas is monitored by the monitoring device, the system automatically isolates the third isolation valve 43 and stops discharging the unqualified waste gas; and the system automatically opens the seventh isolation valve 47, the unqualified waste gas enters the gas recovery unit 23 for recycling treatment, namely, the unqualified waste gas is recycled to the retention treatment unit 21 for retention decay again, and the system can be triggered to open the third isolation valve 43 to discharge the waste gas after the unqualified waste gas is monitored by the monitoring unit 22 again.
According to the characteristics of high yield of beta rays of Kr-85 and weak beta ray penetration capacity, a plastic scintillator beta sensitive detector with the thickness of 0.2mm is adopted as the monitoring device, an online monitoring mode is applied, as shown in figure 1, the online monitoring mode comprises the steps that the monitoring device is inserted into a measuring cavity, the monitoring device is directly immersed into hydrogen-containing waste gas, and beta rays released by Kr-85 in the waste gas are directly measured, so that the online continuous monitoring of the activity of the hydrogen-containing waste gas is realized, the measurement accuracy of the activity of Kr and Xe in the hydrogen-containing waste gas is improved, and the explosion risk of leakage of the hydrogen-containing waste gas is eliminated. Considering that the measuring object of the monitoring device is hydrogen-containing radioactive waste gas, the leakage of the waste gas is caused by the risk of explosion of hydrogen, and the gas leakage rate of the monitoring device is lower than 6.58 multiplied by 10 -9 Pa·m 3 And the explosion-proof grade is Ex diiCT 6 Gb.
In other embodiments, the number of the monitoring devices may be two, which includes the first monitoring device 221 and the second monitoring device 222 arranged in parallel; the working mode of the first monitoring device 221 and the second monitoring device 222 is one-use-one-standby, that is, when the first monitoring device 221 is in the working state, the second monitoring device 222 enters the standby state; when the second monitoring device 222 is in the working state, the first monitoring device 221 enters a standby state; the gas recovery unit 23 comprises a seventh isolation valve 47, an eighth isolation valve 48, a circulation pump and a ninth isolation valve 49; one path of the outlet of the detention processing unit 21 is connected with the first end of the first monitoring device 221 through a first isolation valve 41, and the other path is connected with the first end of the second monitoring device 222 through a second isolation valve 42; one path of the second end of the first monitoring device 221 is connected to the inlet of the retention treatment unit 21 through a seventh isolation valve 47, a circulating pump and a ninth isolation valve 49 in sequence, and the other path is connected to the inlet of the filtering and discharging unit 3 through a third isolation valve 43; the second monitoring device 222 has a second end connected to the inlet of the retention treatment unit 21 through the eighth isolation valve 48, the circulation pump and the ninth isolation valve 49 in this order, and the other end connected to the inlet of the filtering and discharging unit 3 through the fourth isolation valve 44.
Further, the filtering and discharging unit 3 further includes an exhaust device 33 for discharging the exhaust gas, specifically, the exhaust device 33 may be a chimney, and the exhaust gas after being filtered by the first filtering branch 31 or the second filtering branch 32 is discharged to the external environment through the exhaust device 33. Specifically, the first filtering branch may be referred to as an aerosol filter discharge branch, the first filtering branch 31 includes a fifth isolation valve 45 and an aerosol filter 311, and an outlet of the monitoring unit 22 is connected to the exhaust device 33 through the fifth isolation valve 45 and the aerosol filter 311 in sequence. The second filtering branch may be referred to as an iodine filter discharging branch, the second filtering branch 32 includes a sixth isolation valve 46 and an iodine filter 322, and one path of the outlet of the monitoring unit 22 is connected to the exhaust device 33 through the sixth isolation valve 46 and the iodine filter 322.
Further, the system for treating the hydrogen-containing radioactive waste gas from the nuclear power plant further comprises a gas monitor 35, wherein the gas monitor 35 is disposed on the exhaust device 33 and is used for monitoring the waste gas in the exhaust device 33. If the radioactivity of the exhaust gas measured by the gas monitor 35 exceeds a set threshold, the interlocking action is also triggered to stop the exhaust gas emission of the exhaust gas treatment system.
Further, the filtering and discharging unit 3 further includes a ventilation device 34, the ventilation device 34 is disposed on the pipeline between the monitoring unit 22 and the filtering and discharging unit 3, and the ventilation device 34 exhausts air to dilute the exhaust air which is monitored by the monitoring unit 22 and then discharged to the first filtering branch 31 or the second filtering branch 32. During the operation of the hydrogen-containing radioactive waste gas treatment system in the nuclear power plant, the waste gas entering the hydrogen-containing radioactive waste gas treatment system in the nuclear power plant must be measured by the first monitoring device 221 or the second monitoring device 222 to be qualified, and then can be continuously treated by entering the filtering and discharging unit 3, and the radioactive waste gas is discharged to the exhaust pipeline of the ventilation device 34, is exhausted and diluted by the ventilation device 34, enters the first filtering branch 31 or the second filtering branch 32 for filtering, and is discharged to the environment by the chimney after being monitored by the gas monitor 35.
As shown in fig. 2, the present invention further provides a method for treating hydrogen-containing radioactive waste gas from a nuclear power plant, which is suitable for the system for treating hydrogen-containing radioactive waste gas from a nuclear power plant, and includes step S1 of obtaining a monitoring result of the monitoring unit 22, determining whether the monitoring result exceeds a set threshold, switching to the first filtering branch 31 or the second filtering branch 32 to filter waste gas, and controlling to switch on or off the gas recovery unit 23. Wherein the set threshold comprises a first threshold and a second threshold, the first threshold determines the filtering mode of the filtering and discharging unit 3, and the second threshold determines whether the exhaust gas stops discharging and enters the gas recovery unit 23 for recycling and processing. The monitoring result comprises the radioactivity activity concentration of the hydrogen-containing radioactive waste gas; in this embodiment, the concentration of the activity of the hydrogen-containing radioactive waste gas is mainly monitored, and whether to trigger an alarm or perform a related operation is determined according to the comparison between the concentration of the activity of the hydrogen-containing radioactive waste gas and a set threshold; the monitoring unit 22 mainly monitors the activity concentration of the exhaust gas currently discharged and flowing through the first monitoring device 221 or the second monitoring device 222, and if the exhaust gas is qualified through monitoring by the monitoring device, the monitoring unit triggers the related isolating valve to open or isolate, and switches to the first filtering branch 31 or the second filtering branch 32 for filtering the exhaust gas, so that the exhaust gas is discharged through the filtering and discharging unit 3; if unqualified waste gas is monitored by the monitoring device, the related isolating valve is triggered to be opened or isolated, so that the gas recovery unit 23 is controlled to be switched on or switched off, and the waste gas entering the gas recovery unit 23 is recycled.
Further, step S1 specifically includes:
s11, judging whether the monitoring results are all larger than a first threshold value within a first preset time, namely judging whether a monitoring device in the monitoring unit 22 triggers a primary alarm; if yes, executing step S12, otherwise, switching to the first filtering branch 31 for filtering the exhaust gas;
s12, switching to a second filtering branch 32 to filter the waste gas, and continuously judging whether the monitoring result is greater than a second threshold value within a second preset time, namely judging whether a monitoring device in the monitoring unit 22 triggers a secondary alarm; if yes, executing step S13, otherwise executing step S11; wherein the second threshold is greater than the first threshold; further, the first preset time may be set to 5 seconds, that is, it is determined whether the monitoring result is greater than the first threshold value in 5 seconds, if yes, step S12 is executed, and if not, the first filtering branch 31 is switched to perform exhaust gas filtering; understandably, the second preset times may be set to 5 seconds, that is, it is determined whether the monitoring results are greater than the second threshold value in 5 seconds, if yes, step S13 is executed, and if no, step S11 is executed; the purpose is to prevent false alarm triggering caused by the pulse signal, and generally, the pulse signal lasts for tens of milliseconds, so the first preset time and the second preset time can be selected according to actual conditions, and are not limited herein.
S13, stopping discharging the waste gas to the filtering and discharging unit 3, and automatically triggering and switching on the gas recovery unit 23 to perform waste gas circulation treatment; understandably, unqualified waste gas can be recovered and monitored by the storage tank, and the waste gas with excessive radioactivity is collected by the storage tank to realize the long-time storage decay function of the radioactive waste gas.
As shown in fig. 3 to 6, the operation mode of the first monitoring device 221 and the second monitoring device 222 is one-use-one-standby, that is, when the first monitoring device 221 is in the operation state, the second monitoring device 222 enters the standby state; and vice versa. When the radioactivity of the inert gas in the exhaust gas discharged by the exhaust gas treatment system measured by the first monitoring device 221 or the second monitoring device 222 exceeds a set threshold value, an interlocking action is triggered, and the system triggers and implements the control of the discharge of the hydrogen-containing exhaust gas. Specifically, the interlock control requires the following:
(1) If the concentration of the radioactivity activity of the discharged exhaust gas is less than a first threshold, specifically, the value of the first threshold can be 1.8E +07Bq/m 3 The radioactive exhaust gas is exhausted to the exhaust duct of the ventilation device 34, filtered by the aerosol filter 311 in the first filtering branch 31, and then exhausted to the chimney.
(2) If the radioactivity concentration of the discharged waste gas is greater than the first threshold value, the first monitoring device 221 or the second monitoring device 222 triggers a primary alarm signal and automatically interlocks to open the sixth isolation valve 46 and isolate the fifth isolation valve 45, so that the waste gas discharge is switched from the first filtering branch 31 to the second filtering branch 32, and the radioactive waste gas is filtered by the iodine filter 322 and then discharged to a chimney.
(3) If the radioactivity concentration of the exhaust gas is greater than the second threshold, specifically, the second threshold may be 2.2E +08Bq/m 3 Exhaust gas emissionThe first monitoring device 221 or the second monitoring device 222 triggers a second-level alarm signal, automatically opens the seventh isolating valve 47 or the eighth isolating valve 48, opens the circulating pump and the ninth isolating valve 49, automatically isolates the hydrogen-containing waste gas to discharge the first isolating valve 41 and the second isolating valve 42, stops the discharge of the waste gas, and sends the hydrogen-containing radioactive waste gas to the retention treatment unit 21 for circulating and retreating, so that the activity concentration of iodine and inert gas in the waste gas is further reduced.
(4) If the activity concentration of the discharged waste gas is less than or equal to 70% of the first threshold value, the first-level alarm is removed, the fifth isolation valve 45 is automatically interlocked and opened, the sixth isolation valve 46 is isolated, the waste gas discharge is switched to the first filtering branch 31 from the second filtering branch 32 to realize the normal discharge of the waste gas, and the radioactive waste gas is filtered by the aerosol filter 311 and then discharged to a chimney.
(5) After the hydrogen-containing waste gas is sent to the retention treatment unit 21 by the circulating pump for further treatment, the radioactive activity concentrations of inert gas and iodine in the waste gas can be further reduced. When the measurement result of the first monitoring device 221 or the second monitoring device 222 is less than or equal to 70% of the second threshold value, the second-level alarm is relieved, the third isolation valve 43 or the fourth isolation valve 44 is automatically opened, the seventh isolation valve 47 or the eighth isolation valve 48 is automatically isolated, and the circulating pump is isolated, so that the hydrogen-containing waste gas is monitored and discharged on line.
(6) If the first monitoring device 221 fails and triggers a fault alarm, the interlock automatically opens the second isolation valve 42 and isolates the first isolation valve 41, the second monitoring device 222 is activated to change from the standby state to the working mode, and the second monitoring device 222 completes monitoring to realize exhaust gas monitoring and emission. If the second monitoring device 222 triggers a fault alarm when a fault occurs, the first isolation valve 41 is automatically opened and the second isolation valve 42 is isolated by interlocking, the first monitoring device 221 is activated to change from the standby state to the working mode, and the first monitoring device 221 completes monitoring to realize exhaust gas monitoring and emission.
First monitoring device 221 or second monitoring device 222IsAutomatic control logic for two-level alarms referring to fig. 3 and 4, the first monitoring device 221 or the second monitoring device 222IsThe automatic control logic for two-stage alarm release is the reverse process of the two-stage alarm automatic control logic, i.e. the first monitoring device 221 or the second monitoring deviceThe automatic control logic of the second monitoring device 222 in case of a fault alarm is shown in fig. 5 and 6.
When the radioactivity of the waste gas measured by the gas monitor 35 exceeds a set threshold value, the interlocking action is also triggered to stop the waste gas emission of the waste gas treatment system. The gas monitor 35 measures whether the activity concentration of the inert gas in the stack exhaust gas exceeds a second threshold value on line, if so, an alarm is triggered and the exhaust gas emission of the exhaust gas treatment system is automatically stopped, and the control requirement of the gas monitor is the same as that of the first monitoring device 221 or the second monitoring device 222 for triggering a secondary alarm.
The first monitoring device 221 or the second monitoring device 222 measures the activity concentration of the inert gas on line, and the first threshold value is 1.8E +07Bq/m 3 The derived air concentration of the gas-borne iodine in the exhaust gas corresponding to the exhaust gas treatment system is less than 0.1DAC, and the radioactivity activity concentration of the iodine is 2.98E +02Bq/m 3 Second threshold value (2.2E +08Bq/m 3 ) The radioactivity activity concentration of the gas-borne iodine in the exhaust gas corresponding to the exhaust gas treatment system is 3.7E +03Bq/m 3 。
The invention solves the problems of monitoring the emission of the hydrogen-containing radioactive waste gas and controlling the treatment of iodine in the emission of the radioactive waste gas, and prolongs the retention decay time of the radioactive waste gas by improving the waste gas treatment process. The method adopts an explosion-proof beta sensitive detector with low gas leakage rate, and uses an online monitoring mode to continuously monitor the activity concentration of the hydrogen-containing waste gas on line, thereby realizing the automatic control of the hydrogen-containing waste gas emission of the waste gas treatment system. The invention mainly has the following technical effects:
1. according to the characteristics of Kr-85 that the gamma ray yield is 0.43 percent and the beta ray yield is 99.57 percent and the characteristic that hydrogen-containing waste gas is easy to explode, an explosion-proof beta sensitive detector with extremely low leakage rate is adopted, and an online monitoring mode is used for continuously measuring the radioactivity concentration of the discharged waste gas on line, so that the accuracy of measuring the activity of the discharged waste gas is improved, the risk of leakage and explosion in the measuring process of the hydrogen-containing waste gas is eliminated, and the operation safety of a nuclear power plant is improved.
2. The on-line continuous measurement cancels the analysis work items of the discharged waste gas sampling laboratory in the waste gas storage tank treatment process, and reduces the workload and the irradiated dose of radiochemistry workers.
3. The system requires the exhaust emission to be switched to the second filtering branch through the primary alarm interlocking control, and the radioactivity concentration of iodine in the exhaust emission to the environment can be reduced for the exhaust treatment system adopting the detention bed treatment process.
4. The continuous monitoring of the exhaust emission, the management of the exhaust emission and the automation of control are realized, and the phenomenon that radioactive exhaust gas is discharged by mistake due to insufficient decay caused by human errors is reduced. The start of the iodine filter of the ventilation system is controlled by the primary alarm of exhaust emission monitoring, the replacement frequency of the iodine filter is increased from once replacement in 2 years to once replacement in 5 years, the service cycle of the iodine filter is prolonged, and the amount of solid waste of a nuclear power plant is reduced.
It should be understood that the above examples only represent the preferred embodiments of the present invention, and the description is specific and detailed, but not construed as limiting the scope of the present invention; it should be noted that, for those skilled in the art, the above technical features can be freely combined, and several changes and modifications can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention; therefore, all equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
Claims (18)
1. A nuclear power plant hydrogen-containing radioactive waste gas treatment system is characterized by comprising a pretreatment unit, a treatment loop and a filtering and discharging unit; the treatment loop comprises a retention treatment unit, a monitoring unit and a gas recovery unit, wherein an inlet of the pretreatment unit is connected with the main loop of the nuclear power plant, an outlet of the pretreatment unit is connected with an inlet of the retention treatment unit, and an outlet of the retention treatment unit is connected with an inlet of the monitoring unit; one path of an outlet of the monitoring unit is connected with an inlet of the gas recovery unit, and the other path of the outlet of the monitoring unit is connected with an inlet of the filtering and discharging unit; the outlet of the gas recovery unit is connected with the inlet of the retention treatment unit; the filtering and discharging unit comprises a first filtering branch and a second filtering branch which are arranged in parallel, and an outlet of the filtering and discharging unit is communicated with the external environment;
the hydrogen-containing radioactive waste gas of the nuclear power plant enters the treatment loop for decay and monitoring after the pretreatment unit is used for pressure regulation and drying, and the hydrogen-containing radioactive waste gas passes through the filtering and discharging unit and is discharged into the external environment.
2. The system of claim 1, wherein the pre-treatment unit comprises a compressor and a dryer, and the hydrogen-containing radioactive waste gas from the nuclear power plant is pressurized by the compressor and then discharged to the dryer for drying treatment.
3. The system of claim 2, wherein the pre-treatment unit further comprises a buffer tank, a first end of the buffer tank is connected to the primary loop of the nuclear power plant, and a second end of the buffer tank is connected to the first end of the compressor, and is configured to collect the hydrogen-containing radioactive waste gas generated by the primary loop of the nuclear power plant.
4. The system of claim 2 or 3, wherein the pre-treatment unit further comprises a gas cooler, wherein a first end of the gas cooler is connected to the second end of the compressor, and a second end of the gas cooler is connected to the first end of the dryer.
5. The nuclear power plant hydrogen-containing radioactive waste gas treatment system according to claim 2, wherein the dryer is a silica gel dryer.
6. The nuclear power plant hydrogen-containing radioactive off-gas treatment system according to claim 1, wherein the retention treatment unit includes at least one retention bed of activated carbon, at least one of the retention beds of activated carbon being connected to an outlet of the pretreatment unit.
7. The nuclear power plant hydrogen-containing radioactive waste gas treatment system according to claim 6, wherein the provided number of the activated carbon retention beds is two, which includes a first activated carbon retention bed and a second activated carbon retention bed; and waste gas at the outlet of the pretreatment unit sequentially passes through the first activated carbon retention bed and the second activated carbon retention bed for retention and decay.
8. The system for treating exhaust gas containing hydrogen radioactivity of nuclear power plant according to claim 1, wherein the system for treating exhaust gas containing hydrogen radioactivity of nuclear power plant is further provided with a pressure regulating valve for regulating the pressure of the exhaust gas containing hydrogen radioactivity of nuclear power plant; the pressure regulating valve is disposed between the pretreatment unit and the retention treatment unit.
9. The system of claim 1, wherein the monitoring unit comprises at least one monitoring device for monitoring the exhaust gas at the outlet of the retention treatment unit, a first end of the monitoring device is connected to the outlet of the retention treatment unit, a second end of the monitoring device is connected to the inlet of the gas recovery unit, and another end of the monitoring device is connected to the inlet of the filtering and discharging unit.
10. The nuclear power plant hydrogen-containing radioactive waste gas treatment system according to claim 9, wherein the monitoring devices are provided in number of one, and the gas recovery unit includes a seventh isolation valve, a circulation pump, and a ninth isolation valve;
the outlet of the retention treatment unit is connected with the first end of the monitoring device through a first isolation valve, one path of the second end of the monitoring device is connected to the inlet of the retention treatment unit through the seventh isolation valve, the circulating pump and the ninth isolation valve in sequence, and the other path of the second end of the monitoring device is connected to the inlet of the filtering and discharging unit through a third isolation valve.
11. The system of claim 9, wherein the monitoring devices are provided in two numbers, and comprise a first monitoring device and a second monitoring device arranged in parallel; the gas recovery unit comprises a seventh isolation valve, an eighth isolation valve, a circulating pump and a ninth isolation valve;
one path of an outlet of the detention processing unit is connected with a first end of the first monitoring device through a first isolation valve, and the other path of the outlet of the detention processing unit is connected with a first end of the second monitoring device through a second isolation valve;
one path of the second end of the first monitoring device is connected to the inlet of the retention treatment unit through the seventh isolation valve, the circulating pump and the ninth isolation valve in sequence, and the other path of the second end of the first monitoring device is connected to the inlet of the filtration and discharge unit through the third isolation valve; and one path of the second end of the second monitoring device is connected to the inlet of the retention treatment unit through the eighth isolation valve, the circulating pump and the ninth isolation valve in sequence, and the other path of the second end of the second monitoring device is connected to the inlet of the filtering and discharging unit through the fourth isolation valve.
12. The system of claim 1, wherein the filtering and discharging unit further comprises an exhaust device for discharging the exhaust gas, and the exhaust gas filtered by the first filtering branch or the second filtering branch is discharged to the external environment through the exhaust device.
13. The system of claim 12, wherein the first filtering branch comprises a fifth isolation valve and an aerosol filter, and an outlet of the monitoring unit is connected to the exhaust device through the fifth isolation valve and the aerosol filter in sequence.
14. The system of claim 12, wherein the second filtering branch comprises a sixth isolation valve and an iodine filter, and an outlet of the monitoring unit is connected to the exhaust device through the sixth isolation valve and the iodine filter in sequence.
15. The system of claim 12, further comprising a gas monitor disposed on the exhaust for monitoring exhaust gases in the exhaust.
16. The system of claim 12, wherein the filtering and discharging unit further comprises a ventilation device disposed on a pipeline between the monitoring unit and the filtering and discharging unit, and the ventilation device exhausts and dilutes the exhaust gas that is monitored by the monitoring unit and then discharged to the first filtering branch or the second filtering branch.
17. A method for treating hydrogen-containing radioactive waste gas from a nuclear power plant, which is applied to the hydrogen-containing radioactive waste gas treatment system from any one of claims 1 to 16, and which comprises the following steps:
s1, acquiring a monitoring result of the monitoring unit, switching to the first filtering branch or the second filtering branch according to the monitoring result to filter waste gas, and controlling to switch on or switch off the gas recovery unit; wherein the monitoring result comprises the concentration of the activity of the hydrogen-containing radioactive off-gas.
18. The method for treating the hydrogen-containing radioactive waste gas from the nuclear power plant according to claim 17, wherein the step S1 specifically comprises:
s11, judging whether the monitoring results are larger than a first threshold value within a first preset time, if so, executing a step S12, and if not, switching to the first filtering branch for waste gas filtering;
s12, switching to the second filtering branch for filtering the waste gas, and continuously judging whether the monitoring result is greater than a second threshold value within second preset time, if so, executing a step S13, otherwise, executing a step S11; wherein the second threshold is greater than the first threshold;
and S13, stopping discharging the waste gas to the filtering and discharging unit, and automatically triggering and connecting the gas recovery unit to perform waste gas circulation treatment.
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