CN216902273U - Nuclear power plant reactor primary circuit coolant leakage monitoring system - Google Patents
Nuclear power plant reactor primary circuit coolant leakage monitoring system Download PDFInfo
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- CN216902273U CN216902273U CN202121418369.6U CN202121418369U CN216902273U CN 216902273 U CN216902273 U CN 216902273U CN 202121418369 U CN202121418369 U CN 202121418369U CN 216902273 U CN216902273 U CN 216902273U
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The utility model discloses a nuclear power plant reactor primary circuit coolant leakage monitoring system, which comprises an air inlet channel, a monitoring channel and a return channel which are sequentially connected, and a monitoring equipment assembly arranged on the monitoring channel, wherein an air suction pump is arranged on the return channel; the monitoring channel comprises an F-18 fine dust detection branch and an inert gas detection branch which are connected between the gas inlet channel and the return channel in parallel. According to the utility model, the F-18 micro-dust detector and the inert gas detector are arranged in parallel, the micro-dust filtering mechanism is arranged in front of the inert gas detector, so that the monitoring channel is divided into two independent monitoring branches, the monitoring process is not disturbed, when micro-dust contained in the gas in the containment vessel needs to be independently researched, a sampling result in the micro-dust filtering mechanism is extracted, the sampling result is not disturbed by sampling of the F-18 micro-dust detector, the research result is more comprehensive and accurate, and the monitoring effect is good.
Description
Technical Field
The utility model belongs to the technical field of nuclear power plant reactor primary circuit coolant leakage monitoring, and particularly relates to a nuclear power plant reactor primary circuit coolant leakage monitoring system.
Background
In a pressurized water reactor nuclear power plant, nuclear fuel element cladding damage and neutron activation of corrosion products in primary circuit water generally contain radioactive nuclides in reactor coolant, and meanwhile, the primary circuit water is high-temperature and high-pressure water, so that once leakage occurs on a primary circuit pressure boundary, the safe operation of a reactor is affected, and radioactive pollution to the environment is caused. Therefore, the leakage of the pressure boundary of the primary circuit is monitored and found in time (the leakage of cracks and crackles and the like caused by welding and mechanical interface sealing parts in the primary circuit reactor body and the pipeline due to the reasons of thermal fatigue cracking (thermal stress), corrosion, irradiation and the like is prevented), the integrity of the pressure boundary of the primary circuit is ensured, and the method is very important for the safe operation of the reactor.
The integrity of the primary pressure boundary of a reactor of a pressurized water reactor nuclear power plant is one of the important conditions for ensuring safe operation of the nuclear power plant. The top cover flange joint of the pressure vessel in the pressure boundary of the primary loop of the reactor, the welding parts of the driving mechanism, the mechanical interfaces in the loop, the valves and other parts are easy to crack under the action of stress corrosion caused by cooling water in the primary loop and pressure corrosion between welding seam crystals, so that the cooling water of the primary loop is easy to leak. If not discovered in time, the cracks become larger and larger, and more leakage occurs. Leakage will have two serious consequences: firstly, the reactor is insufficient in cooling water amount, so that the safety accident of the operation of the reactor is caused; secondly, radioactive substances contained in the primary loop water pollute the environment and cause harm to human bodies. Fission products and corrosion activation products carried in a primary loop coolant have strong radioactivity, and the radioactivity in the air of a containment vessel can be enhanced when primary loop water leaks, so that the leakage condition of a primary loop pressure boundary can be judged by monitoring the radioactive aerosol, iodine-131 and inert gas activity concentration in the containment vessel and monitoring the change of the radioactive activity concentration of F-18 particles in the atmosphere of the containment vessel.
In the prior art, the radioactivity monitoring device is connected in series in a sampling loop for monitoring, but when the radioactivity of the aerosol and the iodine needs to be analyzed independently, the system firstly pumps the gas into the F-18 detection device for detection, and a filter paper device and other devices for filtering the aerosol are necessarily arranged in the F-18 detection device, so that the special aerosol and iodine filtering device in the system cannot completely collect the aerosol and the iodine in the gas, and the radioactivity of the aerosol and the iodine cannot be analyzed independently.
SUMMERY OF THE UTILITY MODEL
The utility model aims to solve the technical problem that the defects in the prior art are overcome, and provides a nuclear power plant reactor primary circuit coolant leakage monitoring system which is simple in structure, reasonable in design and high in practicability, an F-18 micro dust detector and an inert gas detector are arranged in parallel, a micro dust filtering mechanism is arranged in front of the inert gas detector, a monitoring channel is enabled to be two independent monitoring branches, the monitoring process is not disturbed, when micro dust contained in a containment vessel needs to be independently researched, a sampling result in the micro dust filtering mechanism is extracted, the sampling result is not disturbed by sampling of the F-18 micro dust detector, the research result is more comprehensive and accurate, and the monitoring effect is good.
In order to solve the technical problems, the utility model adopts the technical scheme that: a nuclear power plant reactor primary circuit coolant leakage monitoring system which characterized in that: the device comprises an air inlet channel, a monitoring channel, a backflow channel and a monitoring equipment assembly, wherein the air inlet channel, the monitoring channel and the backflow channel are sequentially connected, and the monitoring equipment assembly is arranged on the monitoring channel;
the monitoring channel comprises an F-18 micro dust detection branch and an inert gas detection branch which are connected in parallel between the gas inlet channel and the return channel;
the monitoring equipment assembly comprises an F-18 micro dust detector arranged on an F-18 micro dust detection branch, and a micro dust filtering mechanism and an inert gas detector which are connected in series on an inert gas detection branch, wherein the air inlet end of the inert gas detector is connected with the air outlet end of the micro dust filtering mechanism, and a differential pressure gauge is arranged between the air inlet end and the air outlet end of the F-18 micro dust detector.
The nuclear power plant reactor primary circuit coolant leakage monitoring system is characterized in that: the F-18 micro-dust detection branch is provided with a first regulating valve positioned at the air inlet end of the F-18 micro-dust detector, a first flow meter and a second regulating valve, and the first flow meter is connected with the air outlet end of the F-18 micro-dust detector.
The nuclear power plant reactor primary circuit coolant leakage monitoring system is characterized in that: and a second flowmeter and a third regulating valve are arranged on the inert gas detection branch, and the second flowmeter is connected with the gas outlet end of the inert gas detector.
The nuclear power plant reactor primary circuit coolant leakage monitoring system is characterized in that: the dust filter mechanism comprises two groups of dust filter units which are connected in parallel, each dust filter unit comprises a dust filter and a fourth adjusting valve arranged at the air inlet end of the dust filter, the air inlet end of the fourth adjusting valve is connected with the air inlet channel through an inert gas detection branch, and the air outlet end of the dust filter is connected with the air inlet end of the inert gas detector.
The nuclear power plant reactor primary circuit coolant leakage monitoring system is characterized in that: and the signal output ends of the F-18 micro-dust detector and the inert gas detector are connected with the on-site processing box.
The nuclear power plant reactor primary circuit coolant leakage monitoring system is characterized in that: and a back flushing pipe is arranged on the air inlet channel.
Compared with the prior art, the utility model has the following advantages:
1. the air pump provided by the utility model is used for pumping the gas in the containment vessel into the air inlet channel, and the gas flows through the monitoring channel and the backflow channel in sequence and flows back into the containment vessel, so that the gas in the containment vessel is prevented from leaking in the monitoring process, and the environmental safety is ensured.
2. The utility model is provided with the differential pressure gauge for detecting the air pressure difference between the air inlet end and the air outlet end of the F-18 micro dust detector and judging whether filter paper used for filtering micro dust in the F-18 micro dust detector is blocked or damaged, if so, the detection value of the differential pressure gauge exceeds a threshold value, and if the filter paper is damaged, the detection value of the differential pressure gauge approaches zero.
In conclusion, the utility model has the advantages of simple structure, reasonable design and strong practicability, the F-18 micro dust detector and the inert gas detector are arranged in parallel, the micro dust filtering mechanism is arranged in front of the inert gas detector, the monitoring channel becomes two independent monitoring branches, the monitoring process is not disturbed, when the micro dust contained in the gas in the containment needs to be independently researched, the sampling result in the micro dust filtering mechanism is extracted, the sampling result can not be disturbed by the F-18 micro dust detector, the research result is more comprehensive and accurate, and the monitoring effect is good.
The technical solution of the present invention is further described in detail by the accompanying drawings and embodiments.
Drawings
FIG. 1 is a schematic diagram of the system of the present invention.
Description of reference numerals:
1-an intake passage; 2-a return channel; 3-an air pump;
4-F-18 micronic dust detection branch; 5-an inert gas detection branch; 6-F-18 mote detector;
7-inert gas detector; 8-a differential pressure gauge; 9-a containment vessel;
10-a first regulating valve; 11-a second regulating valve; 12-a first flow meter;
13-a second flow meter; 14-a third regulating valve; 15-a fine dust filter;
16-a fourth regulating valve; 17-in-situ treatment tank; 18-backwash tube.
Detailed Description
As shown in fig. 1, the present invention includes an air intake passage 1, a monitoring passage and a return passage 2, which are connected in sequence, and a monitoring device assembly disposed on the monitoring passage, wherein an air pump 3 is disposed on the return passage 2;
the monitoring channel comprises an F-18 fine dust detection branch 4 and an inert gas detection branch 5 which are connected between the gas inlet channel 1 and the return channel 2 in parallel;
the monitoring equipment component comprises an F-18 micro dust detector 6 arranged on an F-18 micro dust detection branch 4, a micro dust filtering mechanism and an inert gas detector 7 which are connected in series on an inert gas detection branch 5, wherein the air inlet end of the inert gas detector 7 is connected with the air outlet end of the micro dust filtering mechanism, and a differential pressure gauge 8 is arranged between the air inlet end and the air outlet end of the F-18 micro dust detector 6.
It should be noted that the air pump 3 pumps the gas in the containment 9 into the air inlet channel 1, and the gas flows through the monitoring channel and the backflow channel 2 in sequence and flows back into the containment 9, so that the gas in the containment 9 is prevented from leaking in the monitoring process, and the environmental safety is ensured.
It should be noted that, by arranging the F-18 dust particle detector 6 and the inert gas detector 7 in parallel, and arranging the dust particle filtering mechanism in front of the inert gas detector 7, the monitoring channel becomes two separate monitoring branches, the monitoring process is not disturbed, when the dust particles contained in the gas in the containment 9 need to be studied separately, the sampling result in the dust particle filtering mechanism can be extracted, and the sampling result is not disturbed by the sampling of the F-18 dust particle detector 6, so that the research result is more comprehensive and accurate, and the monitoring effect is good.
It should be noted that the differential pressure gauge 8 is arranged to detect the air pressure difference between the air inlet end and the air outlet end of the F-18 fine dust detector 6, and is used to determine whether the filter paper used for filtering fine dust in the F-18 fine dust detector 6 is blocked or damaged, if so, the detection value of the differential pressure gauge 8 exceeds the threshold value, and if the filter paper is damaged, the detection value of the differential pressure gauge 8 approaches zero.
In the embodiment, the F-18 fine dust detector 6 adopts an F-18 fine dust detection device in the utility model patent 'system and method for quantitatively measuring the leakage rate of the primary circuit coolant of a pressurized water reactor nuclear power plant' with the application number of 201310011880.8; the inert gas detector 7 adopts an inert gas detection device in the utility model patent of system and method for quantitatively measuring the leakage rate of the primary circuit coolant of a pressurized water reactor nuclear power plant with the application number of 201310011880.8.
It should be noted that when the power of the nuclear reactor is less than 20% of the full power, the nuclear reaction generates few F-18 nuclides, the monitoring result of the F-18 dust detector 6 will not be representative, and the inert gas detector 7 can be used to qualitatively measure the leakage of the reactor coolant. When the power of the nuclear reactor is less than 20% of full power, the detection data of the F-18 dust detector 6 is not collected, and the inert gas detector 7 is adopted to measure the total beta activity concentration of the inert gas in the sampling gas chamber.
In this embodiment, the F-18 fine dust detection branch 4 is provided with a first regulating valve 10, a first flowmeter 12 and a second regulating valve 11, which are located at an air inlet end of the F-18 fine dust detector 6, and the first flowmeter 12 is connected with an air outlet end of the F-18 fine dust detector 6.
It should be noted that, when the system is working normally, the first regulating valve 10 and the second regulating valve 11 are opened, and when the F-18 fine dust detector 6 needs to be replaced and repaired, the first regulating valve 10 and the second regulating valve 11 are closed, so as to prevent the radioactive gas from leaking.
In this embodiment, the inert gas detection branch 5 is provided with a second flowmeter 13 and a third regulating valve 14, and the second flowmeter 13 is connected with the gas outlet end of the inert gas detector 7.
In this embodiment, the fine dust filtering mechanism includes two sets of fine dust filtering units connected in parallel, the fine dust filtering unit includes a fine dust filter 15 and a fourth adjusting valve 16 disposed at an air inlet end of the fine dust filter 15, an air inlet end of the fourth adjusting valve 16 is connected to the air inlet channel 1 through the inert gas detection branch 5, and an air outlet end of the fine dust filter 15 is connected to an air inlet end of the inert gas detector 7.
It should be noted that, when the system is working normally, the third regulating valve 14 and the fourth regulating valve 16 are opened, and when the inert gas detector 7 needs to be replaced and repaired, the third regulating valve 14 and the fourth regulating valve 16 are closed, so as to prevent the radioactive gas from leaking.
It should be noted that two sets of the fine dust filter units are provided, one for each, and the fourth regulating valve 16 is regulated to determine which set of the fine dust filter 15 is used, so that the shutdown of the monitoring system caused by the failure of the fine dust filter is reduced.
In this embodiment, the dust filter 15 includes an aerosol filter device and a radioactive iodine adsorption device, the aerosol filter device selects "a radioactive aerosol purification device" with application No. 200420092720.7, and the radioactive iodine adsorption device selects "an adsorption device for removing radioactive iodine ions" with application No. 201922324348.7.
In this embodiment, the signal output terminals of the F-18 fine dust detector 6 and the inert gas detector 7 are both connected to the in-situ processing box 17.
In this embodiment, the on-site processing box 17 is a data processing and display unit in the "on-site radiation monitor for nuclear power plant exhaust gas treatment system" of utility model patent No. 201420396520.4.
In this embodiment, the intake passage 1 is provided with a back-flushing pipe 18.
The above description is only a preferred embodiment of the present invention, and is not intended to limit the present invention, and all simple modifications, changes and equivalent structural changes made to the above embodiment according to the technical spirit of the present invention still fall within the protection scope of the technical solution of the present invention.
Claims (6)
1. A nuclear power plant reactor primary circuit coolant leakage monitoring system which characterized in that: the device comprises an air inlet channel (1), a monitoring channel and a backflow channel (2) which are sequentially connected, and a monitoring equipment assembly arranged on the monitoring channel, wherein an air suction pump (3) is arranged on the backflow channel (2);
the monitoring channel comprises an F-18 micro dust detection branch (4) and an inert gas detection branch (5) which are connected in parallel between the gas inlet channel (1) and the return channel (2);
the monitoring equipment assembly comprises an F-18 micro-dust detector (6) arranged on an F-18 micro-dust detection branch (4), a micro-dust filtering mechanism and an inert gas detector (7) which are connected in series on an inert gas detection branch (5), wherein the gas inlet end of the inert gas detector (7) is connected with the gas outlet end of the micro-dust filtering mechanism, and a pressure difference meter (8) is arranged between the gas inlet end and the gas outlet end of the F-18 micro-dust detector (6).
2. The nuclear power plant reactor primary circuit coolant leakage monitoring system of claim 1, characterized in that: the F-18 micro-dust detection branch (4) is provided with a first regulating valve (10) positioned at the air inlet end of the F-18 micro-dust detector (6), a first flow meter (12) and a second regulating valve (11), and the first flow meter (12) is connected with the air outlet end of the F-18 micro-dust detector (6).
3. The nuclear power plant reactor primary circuit coolant leakage monitoring system of claim 1, characterized in that: the inert gas detection branch (5) is provided with a second flowmeter (13) and a third regulating valve (14), and the second flowmeter (13) is connected with the gas outlet end of the inert gas detector (7).
4. The nuclear power plant reactor primary circuit coolant leakage monitoring system of claim 1, characterized in that: the dust filter mechanism comprises two groups of dust filter units which are connected in parallel, each dust filter unit comprises a dust filter (15) and a fourth adjusting valve (16) arranged at the air inlet end of the dust filter (15), the air inlet end of the fourth adjusting valve (16) is connected with the air inlet channel (1) through an inert gas detection branch (5), and the air outlet end of the dust filter (15) is connected with the air inlet end of the inert gas detector (7).
5. The nuclear power plant reactor primary circuit coolant leakage monitoring system of claim 1, wherein: the signal output ends of the F-18 micro-dust detector (6) and the inert gas detector (7) are connected with a local processing box (17).
6. The nuclear power plant reactor primary circuit coolant leakage monitoring system of claim 1, characterized in that: a back flushing pipe (18) is arranged on the air inlet channel (1).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121418369.6U CN216902273U (en) | 2021-06-24 | 2021-06-24 | Nuclear power plant reactor primary circuit coolant leakage monitoring system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202121418369.6U CN216902273U (en) | 2021-06-24 | 2021-06-24 | Nuclear power plant reactor primary circuit coolant leakage monitoring system |
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| Publication Number | Publication Date |
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| CN216902273U true CN216902273U (en) | 2022-07-05 |
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| CN202121418369.6U Active CN216902273U (en) | 2021-06-24 | 2021-06-24 | Nuclear power plant reactor primary circuit coolant leakage monitoring system |
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2021
- 2021-06-24 CN CN202121418369.6U patent/CN216902273U/en active Active
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