CN114720639B - Radiation monitoring system and method for leakage of primary coolant - Google Patents
Radiation monitoring system and method for leakage of primary coolant Download PDFInfo
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- CN114720639B CN114720639B CN202210349463.3A CN202210349463A CN114720639B CN 114720639 B CN114720639 B CN 114720639B CN 202210349463 A CN202210349463 A CN 202210349463A CN 114720639 B CN114720639 B CN 114720639B
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- 230000005855 radiation Effects 0.000 title claims abstract description 68
- 238000012544 monitoring process Methods 0.000 title claims abstract description 59
- 239000002826 coolant Substances 0.000 title claims abstract description 29
- 238000000034 method Methods 0.000 title claims abstract description 19
- 238000005070 sampling Methods 0.000 claims abstract description 102
- 239000000443 aerosol Substances 0.000 claims abstract description 78
- 239000011261 inert gas Substances 0.000 claims abstract description 62
- 238000010926 purge Methods 0.000 claims abstract description 35
- 229910052740 iodine Inorganic materials 0.000 claims abstract description 19
- 239000011630 iodine Substances 0.000 claims abstract description 19
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 claims abstract description 18
- 230000001105 regulatory effect Effects 0.000 claims abstract description 11
- 239000007789 gas Substances 0.000 claims description 38
- 230000000694 effects Effects 0.000 claims description 26
- 238000011065 in-situ storage Methods 0.000 claims description 17
- 238000012545 processing Methods 0.000 claims description 6
- 230000000007 visual effect Effects 0.000 claims description 6
- 230000009471 action Effects 0.000 claims description 3
- 239000002245 particle Substances 0.000 claims description 3
- 230000008569 process Effects 0.000 claims description 3
- 238000001514 detection method Methods 0.000 abstract description 7
- 241000282414 Homo sapiens Species 0.000 abstract description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 239000000498 cooling water Substances 0.000 description 7
- 239000000941 radioactive substance Substances 0.000 description 5
- 238000013461 design Methods 0.000 description 4
- 238000005259 measurement Methods 0.000 description 4
- 238000004891 communication Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000007613 environmental effect Effects 0.000 description 2
- 239000003381 stabilizer Substances 0.000 description 2
- 241000282412 Homo Species 0.000 description 1
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000011010 flushing procedure Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000007257 malfunction Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012806 monitoring device Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 241000894007 species Species 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N33/00—Investigating or analysing materials by specific methods not covered by groups G01N1/00 - G01N31/00
- G01N33/0004—Gaseous mixtures, e.g. polluted air
- G01N33/0009—General constructional details of gas analysers, e.g. portable test equipment
- G01N33/0027—General constructional details of gas analysers, e.g. portable test equipment concerning the detector
- G01N33/0036—General constructional details of gas analysers, e.g. portable test equipment concerning the detector specially adapted to detect a particular component
- G01N33/0055—Radionuclides
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/22—Devices for withdrawing samples in the gaseous state
- G01N1/2226—Sampling from a closed space, e.g. food package, head space
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/22—Devices for withdrawing samples in the gaseous state
- G01N1/24—Suction devices
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/18—Measuring radiation intensity with counting-tube arrangements, e.g. with Geiger counters
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/20—Measuring radiation intensity with scintillation detectors
- G01T1/202—Measuring radiation intensity with scintillation detectors the detector being a crystal
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/20—Measuring radiation intensity with scintillation detectors
- G01T1/203—Measuring radiation intensity with scintillation detectors the detector being made of plastics
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N1/00—Sampling; Preparing specimens for investigation
- G01N1/02—Devices for withdrawing samples
- G01N1/22—Devices for withdrawing samples in the gaseous state
- G01N1/2226—Sampling from a closed space, e.g. food package, head space
- G01N2001/2238—Sampling from a closed space, e.g. food package, head space the gas being compressed or pressurized
-
- 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a loop coolant leakage radiation monitoring system and a loop coolant leakage radiation monitoring method, wherein the system comprises a sampling pipeline, a purging pipeline, an exhaust pipeline, an F-18 aerosol detector and an inert gas detector; the purging pipeline and the exhaust pipeline are both communicated with the sampling pipeline, and a sampling inlet, a first stop valve, a second stop valve, a regulating valve, a flowmeter, a third stop valve and a fourth stop valve are sequentially arranged on the sampling pipeline along the airflow direction; the purging pipeline is sequentially provided with a purging inlet, a fifth stop valve, a one-way valve, a sixth stop valve, an aerosol and iodine filter and a seventh stop valve along with the airflow direction; an eighth stop valve, a first sampling pump, a ninth stop valve, a tenth stop valve and an exhaust port are sequentially arranged on the exhaust pipe along with the airflow direction. The invention can be effectively applied to the atmosphere radiation monitoring of the containment, has high radiation monitoring precision and detection efficiency and good radiation monitoring continuity, and avoids the harm to the environment and human beings.
Description
Technical Field
The invention belongs to the technical field of containment atmospheric radiation monitoring, and particularly relates to a primary loop coolant leakage radiation monitoring system and method.
Background
The nuclear power plant of a pressurized water reactor nuclear power plant is generally composed of two closed circulation loops, namely a primary loop and a secondary loop. A circuit comprises a nuclear reactor (sealed in a pressure vessel), a main cooling water pump, a pressure stabilizer, a primary side of a steam generator and the like, the pressure is kept between 120 and 160 atmospheres; the secondary loop comprises a steam generator, a condenser, a main cooling water pump, a secondary side of the steam generator and other devices, and the pressure is kept at 70 atmospheres. The primary loop connects the core and the steam generator in the secondary loop.
In order to ensure that the radioactive substances in the nuclear reactor do not escape into the environment, avoiding radiation pollution to humans and the environment, all the equipment of the primary circuit and the steam generators in the secondary circuit of the pressurized water reactor nuclear power plant are installed in a containment.
In the containment, the pressure vessel, pressure stabilizer, main cooling water pump, cooling water pipe, primary side equipment of steam generator, and the sealing cover, valve, pipe interface, etc. connected to them form the pressure boundary of the pressurized water reactor coolant system. High temperature and high pressure cooling water within a circuit may break through pressure boundary constraints and leak into the containment vessel for various reasons such as manufacturing, installation, wear, corrosion, etc. This leakage will have two serious consequences: firstly, the cooling water quantity of the reactor is insufficient, so that the operation safety accident of the reactor is caused; and secondly, radioactive substances contained in the primary circuit water enter the environment to cause harm to the environment and human beings. Therefore, the radiation of the leakage of the coolant from the primary circuit must be continuously monitored.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a loop coolant leakage radiation monitoring system aiming at the defects in the prior art, the system is simple in structure, reasonable in design and convenient to realize, can be effectively applied to the atmosphere radiation monitoring of a containment, has high radiation monitoring precision and detection efficiency, good continuity of radiation monitoring, can timely and effectively discover that radioactive substances enter the atmosphere of the containment, avoids harm to the environment and human, has good use effect and is convenient to popularize and use.
In order to solve the technical problems, the invention adopts the following technical scheme: a radiation monitoring system for leakage of a primary loop coolant comprises a sampling pipeline, a purging pipeline, an exhaust pipeline, an F-18 aerosol detector and an inert gas detector; the purging pipeline and the exhaust pipeline are communicated with the sampling pipeline, and the F-18 aerosol detector and the inert gas detector are arranged on the sampling pipeline; the sampling pipeline is sequentially provided with a sampling inlet, a first stop valve, a second stop valve, a regulating valve, a flowmeter, a third stop valve and a fourth stop valve along with the airflow direction, the F-18 aerosol detector is arranged between the second stop valve and the regulating valve, the inert gas detector is arranged between the third stop valve and the fourth stop valve, and a differential pressure meter is arranged between the inlet and the outlet of the F-18 aerosol detector; the purging pipeline is sequentially provided with a purging inlet, a fifth stop valve, a one-way valve, a sixth stop valve, an aerosol and iodine filter and a seventh stop valve along with the airflow direction, one section of the purging pipeline positioned behind the seventh stop valve is communicated with a sampling pipeline, one section of the purging pipeline positioned between the one-way valve and the sixth stop valve is connected with a first connecting pipe, and the other end of the first connecting pipe is communicated with one section of the sampling pipeline positioned between the first stop valve and the second stop valve; the exhaust pipeline is communicated with a section of sampling pipeline positioned behind the fourth stop valve and is communicated with a section of sampling pipeline positioned between the flowmeter and the third stop valve through a second connecting pipe; an eleventh stop valve, an iodine filter and a twelfth stop valve are sequentially arranged on the second connecting pipe along the airflow direction.
According to the first loop coolant leakage radiation monitoring system, the third connecting pipe is connected between the air inlet end of the eighth stop valve and the air outlet end of the ninth stop valve, and the thirteenth stop valve, the second sampling pump and the fourteenth stop valve are sequentially arranged on the third connecting pipe along with the air flow direction.
In the above-mentioned first-loop coolant leakage radiation monitoring system, the F-18 aerosol detector and the inert gas detector are both arranged in the lead shielding chamber.
In the above-mentioned primary loop coolant leakage radiation monitoring system, the sampling pipeline, the purge pipeline, the exhaust pipeline, the first sampling pump, the second sampling pump and the lead shielding chamber are all installed on the integrated bracket.
According to the loop coolant leakage radiation monitoring system, the F-18 aerosol radiation-in-place processor, the inert gas radiation-in-place processor and the electric box are further arranged on the integrated bracket, the F-18 aerosol detector is connected with the F-18 aerosol radiation-in-place processor, and the inert gas detector is connected with the inert gas radiation-in-place processor.
The first chamber and the second chamber are arranged in the shielding shell, the beta-sensitive plastic scintillator detector for detecting beta rays emitted by the F-18 aerosol is arranged in the first chamber, the NaITl detector for detecting gamma rays emitted by the F-18 aerosol is arranged in the second chamber, a filter chamber for sampling the F-18 aerosol is arranged between the beta-sensitive plastic scintillator detector and the NaITl detector, a driving reel and a driven reel are arranged in the filter chamber, and sampling filter paper bridged between the driving reel and the driven reel is arranged in the filter chamber, and the sampling filter paper is stretched between the beta-sensitive plastic scintillator detector and the NaITl detector.
The invention also discloses a method for monitoring leakage radiation of the primary loop coolant, which adopts the system and comprises the following steps:
step one, sampling gas;
the first stop valve is opened, the second stop valve is opened, the third stop valve is opened, the fourth stop valve is opened, the eighth stop valve is opened, the ninth stop valve is opened and the tenth stop valve is opened, and the fifth stop valve is closed, the sixth stop valve is closed, the seventh stop valve is closed, the eleventh stop valve is closed and the twelfth stop valve is closed; under the action of a first sampling pump, gas in the containment sequentially passes through a sampling inlet, a first stop valve and a second stop valve to enter an F-18 aerosol detector;
step two, F-18 aerosol radiation monitoring;
the F-18 aerosol detector pair samples the gas 18 F nuclide activity concentration is detected, and the F-18 aerosol in-situ radiation processor performs data processing and display when 18 F, when the nuclide activity concentration exceeds an alarm threshold, sending an audible and visual alarm signal, and sending the alarm signal to a main control room;
step three, inert gas radiation monitoring;
the sampling gas passing through the F-18 aerosol detector sequentially passes through a regulating valve, a flowmeter and a third stop valve to enter an inert gas detector; the inert gas detector is used for detecting inert gas in the sampled gas 85 Kr、 133 Detecting the total activity concentration of nuclides such as Xe, and the like, wherein the inert gas on-site radiation processor performs data processing and display, and when the activity concentration of the inert gas exceeds an alarm threshold value, an audible and visual alarm signal is sent out and sent to a main control room;
step four, returning the sampling gas;
and the sampled gas passing through the inert gas detector returns to the containment vessel through a fourth stop valve, an eighth stop valve, a first sampling pump, a ninth stop valve, a tenth stop valve and an exhaust port in sequence.
In the first to fourth steps, when the F-18 aerosol detector fails or filter paper needs to be replaced, the second stop valve is closed, the sixth stop valve is opened, the seventh stop valve is closed, and sampling gas flows through the aerosol and iodine filter and then enters the inert gas detector; when the inert gas detector fails or filter paper needs to be replaced, the third stop valve and the fourth stop valve are closed, the eleventh stop valve and the twelfth stop valve are opened, and sampling gas flows through the iodine filter.
According to the primary loop coolant leakage radiation monitoring method, when sampling monitoring is completed and purging is needed, the first stop valve is closed, the fifth stop valve is opened, and purge gas sequentially enters the sampling pipeline through the purge inlet, the fifth stop valve and the one-way valve to be purged, and is discharged through the exhaust pipeline.
In the first loop coolant leakage radiation monitoring method, in the second step, the F-18 aerosol detector samples the gas 18 The specific process for detecting the F nuclide activity concentration comprises the following steps:
step 201, monitoring beta+ particle rays emitted by decay of F-18, and counting;
step 202, monitoring gamma photon rays emitted by decay of F-18, and counting;
step 203, calculating to obtain a beta-gamma coincidence counting rate according to the counting of the digital multipaths;
step 204, calculating according to the beta-gamma coincidence counting rate 18 F nuclide activity concentration.
Compared with the prior art, the invention has the following advantages:
1. the system has the advantages of simple structure, reasonable design and convenient realization.
2. The invention uses F-18 aerosol detector to detect the gas in the containment 18 F, detecting the nuclide activity concentration; inert gas in the containment vessel by an inert gas detector 85 Kr、 133 The total activity concentration of the nuclides such as Xe and the like is detected, so that the leakage of the coolant in the first loop is effectively monitored.
3. According to the invention, the aerosol and iodine filters are connected in parallel on the air path of the F-18 aerosol detector, and the iodine filters are connected in parallel on the air path of the inert gas detector, so that radiation monitoring is uninterrupted by adjusting the opening of each stop valve when faults occur or filter papers need to be replaced, and the continuity of the radiation monitoring is ensured.
4. According to the invention, the F-18 aerosol detector and the inert gas detector are both arranged in the lead shielding chamber, so that the influence of external gamma rays is reduced, the background counting rate is reduced, and the monitoring precision is improved.
5. The invention designs a first sampling pump and a second sampling pump, which are used for one time, when one of the sampling pumps runs, is stopped when overheated or damaged, the other sampling pump is started immediately, and continuous sampling and measurement are ensured.
6. The invention adopts the beta-gamma conforming method to sample the gas 18 F, detecting the nuclide activity concentration, and improving the detection efficiency.
7. The invention can be effectively applied to the radiation monitoring of the atmosphere of the containment, has high radiation monitoring precision and detection efficiency, can timely and effectively discover that radioactive substances enter the atmosphere of the containment, avoids the harm to the environment and human beings, has good use effect and is convenient for popularization and use.
In conclusion, the system disclosed by the invention has the advantages of simple structure, reasonable design and convenience in implementation, can be effectively applied to the radiation monitoring of the atmosphere of the containment, has high radiation monitoring precision and detection efficiency, good continuity of radiation monitoring, can timely and effectively discover that radioactive substances enter the atmosphere of the containment, avoids harm to the environment and human beings, has a good use effect, and is convenient to popularize and use.
The technical scheme of the invention is further described in detail through the drawings and the embodiments.
Drawings
FIG. 1 is a schematic diagram of the system components of the present invention;
FIG. 2 is a schematic diagram of the overall structure of the present invention;
FIG. 3 is a schematic structural view of an F-18 aerosol detector according to the present invention.
Reference numerals illustrate:
1-a sampling pipeline; 2-flushing the pipeline; 3-an exhaust pipeline;
a 4-F-18 aerosol detector; 4-1-a shielding shell; 4-2-a first chamber;
4-3-a second chamber; 4-beta sensitive plastic scintillator detectors;
4-5-NaITl detector; 4-6-filtering chamber; 4-7, a driving reel;
4-8, a driven reel; 4-9-sampling filter paper; 5-an inert gas detector;
6-sampling inlet; 7-a first stop valve; 8-a second stop valve;
9-a regulating valve; 10-a flow meter; 11-a third stop valve;
12-a fourth stop valve; 13—a purge inlet; 14-a fifth shut-off valve;
15-a one-way valve; 16-a sixth shut-off valve; 17-aerosol and iodine filter;
18-seventh shut-off valve; 19-a first connection tube; 20-eighth stop valve;
21-a first sampling pump; 22-a ninth stop valve; 23-tenth stop valve;
24-exhaust port; 25-a second connecting pipe; 26-eleventh stop valve;
27-iodine filter; 28-twelfth stop valve; 29-a third connecting tube;
30-thirteenth shut-off valve; 31-a second sampling pump; 32-fourteenth stop valve;
33—a lead shield; 34-an integrated bracket;
a 35-F-18 aerosol in situ radiation processor; 36-inert gas in situ radiation processor;
37-an electrical box; 38-differential pressure gauge.
Detailed Description
As shown in fig. 1, the primary loop coolant leakage radiation monitoring system of the present invention comprises a sampling pipeline 1, a purge pipeline 2, an exhaust pipeline 3, an F-18 aerosol detector 4 and an inert gas detector 5; the purging pipeline 2 and the exhaust pipeline 3 are communicated with the sampling pipeline 1, and the F-18 aerosol detector 4 and the inert gas detector 5 are arranged on the sampling pipeline 1; the sampling pipeline 1 is sequentially provided with a sampling inlet 6, a first stop valve 7, a second stop valve 8, a regulating valve 9, a flowmeter 10, a third stop valve 11 and a fourth stop valve 12 along with the airflow direction, the F-18 aerosol detector 4 is arranged between the second stop valve 8 and the regulating valve 9, the inert gas detector 5 is arranged between the third stop valve 11 and the fourth stop valve 12, and a differential pressure meter 38 is arranged between the inlet and the outlet of the F-18 aerosol detector 4; the purging pipeline 2 is sequentially provided with a purging inlet 13, a fifth stop valve 14, a one-way valve 15, a sixth stop valve 16, an aerosol and iodine filter 17 and a seventh stop valve 18 along the airflow direction, one section of the purging pipeline 2 positioned behind the seventh stop valve 18 is communicated with the sampling pipeline 1, one section of the purging pipeline 2 positioned between the one-way valve 15 and the sixth stop valve 16 is connected with a first connecting pipe 19, and the other end of the first connecting pipe 19 is communicated with one section of the sampling pipeline 1 positioned between the first stop valve 7 and the second stop valve 8; the exhaust pipeline 3 is sequentially provided with an eighth stop valve 20, a first sampling pump 21, a ninth stop valve 22, a tenth stop valve 23 and an exhaust port 24 along the airflow direction, the exhaust pipeline 3 is communicated with a section of sampling pipeline 1 positioned behind the fourth stop valve 12 and is communicated with a section of sampling pipeline 1 positioned between the flowmeter 10 and the third stop valve 11 through a second connecting pipe 25; an eleventh shut-off valve 26, an iodine filter 27 and a twelfth shut-off valve 28 are sequentially provided on the second connection pipe 25 along the direction of the air flow.
In this embodiment, as shown in fig. 1, a third connection pipe 29 is connected between the air inlet end of the eighth stop valve 20 and the air outlet end of the ninth stop valve 22, and a thirteenth stop valve 30, a second sampling pump 31 and a fourteenth stop valve 32 are sequentially disposed on the third connection pipe 29 along with the air flow direction.
In particular, the first sampling pump 21 and the second sampling pump 31 are used for providing gas sampling power, and in order to ensure continuous sampling and measurement, two sampling pumps, namely the first sampling pump 21 and the second sampling pump 31, are adopted, one is used for one, and after the other is stopped or damaged due to overheat, the other is started immediately, so that the whole monitoring device can be ensured not to stop sampling.
In this embodiment, as shown in FIG. 2, the F-18 aerosol detector 4 and the inert gas detector 5 are both mounted in a lead shielded chamber 33.
In practice, the low-emissivity detection capability of the F-18 aerosol detector 4 and the inert gas detector 5 is improved by reducing the external gamma ray effect through the lead shield chamber 33, reducing the background count rate.
In this embodiment, as shown in fig. 2, the sampling line 1, the purge line 2, the exhaust line 3, the first sampling pump 21, the second sampling pump 31, and the lead shield chamber 33 are all mounted on an integrated bracket 34.
In this embodiment, as shown in fig. 2, the integrated bracket 34 is further provided with an F-18 aerosol in-situ radiation processor 35, an inert gas in-situ radiation processor 36 and an electrical box 37, the F-18 aerosol detector 4 is connected with the F-18 aerosol in-situ radiation processor 35, and the inert gas detector 5 is connected with the inert gas in-situ radiation processor 36.
In specific implementation, the F-18 aerosol in-situ radiation processor 35 comprises an ARM main processor, a display screen and an input keyboard, wherein the I/O port is arranged on the input keyboard, and the display screen displays measurement data according to a set format; inputting corresponding information by a keyboard; the RS485 port transmits or receives data sent by the F-18 aerosol detector 4; the network port realizes communication and data exchange with an external computer; the I/O port receives environmental or measured temperature, pressure and flow signals and outputs alarm or switch control signals. The inert gas in-situ radiation processor 36 comprises an ARM main processor, a display screen and an input keyboard, wherein the I/O port is arranged on the input keyboard, and the display screen displays measurement data according to a set format; inputting corresponding information by a keyboard; the RS485 port transmits or receives data sent by the inert gas detector 5; the network port realizes communication and data exchange with an external computer; the I/O port receives environmental or measured temperature, pressure and flow signals and outputs alarm or switch control signals. The electrical box 37 provides various types of input/output terminals and power supplies.
In this embodiment, as shown in fig. 3, the F-18 aerosol detector 4 includes a shielding housing 4-1, a first chamber 4-2 and a second chamber 4-3 are disposed in the shielding housing 4-1, a β -sensitive plastic scintillator detector 4-4 for detecting β -rays emitted from the F-18 aerosol is disposed in the first chamber 4-2, a NaITl detector 4-5 for detecting γ -rays emitted from the F-18 aerosol is disposed in the second chamber 4-3, a filter chamber 4-6 for sampling the F-18 aerosol is disposed between the β -sensitive plastic scintillator detector 4-4 and the NaITl detector 4-5, a driving filter paper roll 4-7 and a driven filter paper roll 4-8 are disposed in the filter chamber 4-6, and a sampling filter paper 4-9 is bridged between the driving filter paper roll 4-7 and the driven filter paper roll 4-8, and the sampling filter paper 4-9 is stretched between the β -sensitive plastic scintillator detector 4-5 and the NaITl detector 4-5.
The invention discloses a radiation monitoring method for leakage of a primary loop coolant, which comprises the following steps:
step one, sampling gas;
the first shut-off valve 7 is open, the second shut-off valve 8 is open, the third shut-off valve 11 is open, the fourth shut-off valve 12 is open, the eighth shut-off valve 20 is open, the ninth shut-off valve 22 is open and the tenth shut-off valve 23 is open, and the fifth shut-off valve 14 is closed, the sixth shut-off valve 16 is closed, the seventh shut-off valve 18 is closed, the eleventh shut-off valve 26 is closed and the twelfth shut-off valve 28 is closed; under the action of a first sampling pump 21, the gas in the containment sequentially enters the F-18 aerosol detector 4 through a sampling inlet 6, a first stop valve 7 and a second stop valve 8;
step two, F-18 aerosol radiation monitoring;
the F-18 aerosol detector 4 samples the gas 18 F-18 aerosol in situ radiation processor 35 performs data processing and display as the concentration of F species activity is detected 18 F, when the nuclide activity concentration exceeds an alarm threshold, sending an audible and visual alarm signal, and sending the alarm signal to a main control room;
fast neutrons in the pressurized water reactor elastically scatter hydrogen nuclei in the primary water, and the generated high-energy protons react with oxygen nuclei in the water to generate radionuclides 18 F, thus, providing an F-18 aerosol detector 4, detectingMeasuring 18 F, thereby obtaining a pressurized water reactor-loop pressure boundary 18 Leakage rate of F.
Step three, inert gas radiation monitoring;
the sampled gas passing through the F-18 aerosol detector 4 sequentially passes through the regulating valve 9, the flowmeter 10 and the third stop valve 11 to enter the inert gas detector 5; the inert gas detector 5 is used for detecting inert gas in the sampled gas 85 Kr、 133 The total activity concentration of the nuclides such as Xe is detected, the inert gas in-situ radiation processor 36 performs data processing and display, and when the inert gas activity concentration exceeds an alarm threshold, an audible and visual alarm signal is sent out and sent to the main control room;
the radioactive inert gas generated by leakage of the boundary of a loop, mainly including fission products entering the cooling water after the cladding of the fuel element is broken 85 Kr、 133 Xe and its isotopes, if the leakage amount of the first-circuit boundary exceeds the normal range, the monitoring value of the inert gas activity concentration is abnormally increased, and thus, the inert gas detector 5 is provided.
Step four, returning the sampling gas;
the sampled gas passing through the inert gas detector 5 is returned to the containment vessel through the fourth shut-off valve 12, the eighth shut-off valve 20, the first sampling pump 21, the ninth shut-off valve 22, the tenth shut-off valve 23 and the exhaust port 24 in this order.
In this embodiment, in the first to fourth steps, when the F-18 aerosol detector 4 fails or the filter paper needs to be replaced, the second stop valve 8 is closed, the sixth stop valve 16 is opened, the seventh stop valve 18 is closed, and the sampled gas flows through the aerosol and iodine filter 17 and then enters the inert gas detector 5; when the inert gas detector 5 malfunctions or the filter paper needs to be replaced, the third stop valve 11 and the fourth stop valve 12 are closed, the eleventh stop valve 26 and the twelfth stop valve 28 are opened, and the sampling gas flows through the iodine filter 27.
In particular, in order to ensure the continuity of radiation monitoring, the air path of the F-18 aerosol detector 4 is connected with the aerosol and iodine filter 17 in parallel, and the air path of the inert gas detector 5 is connected with the iodine filter 27 in parallel, so that the radiation monitoring is uninterrupted by adjusting the opening of each stop valve when faults occur or filter paper needs to be replaced.
In this embodiment, when the sampling monitoring is completed and the purging needs to be performed, the first stop valve 7 is closed, the fifth stop valve 14 is opened, and the purging gas sequentially enters the sampling pipeline 1 through the purging inlet 13, the fifth stop valve 14 and the check valve 15 to be purged, and is discharged through the exhaust pipeline 3.
In this embodiment, the F-18 aerosol detector 4 in step two samples the gas 18 The specific process for detecting the F nuclide activity concentration comprises the following steps:
step 201, monitoring beta+ particle rays emitted by decay of F-18, and counting;
step 202, monitoring gamma photon rays emitted by decay of F-18, and counting;
step 203, calculating to obtain a beta-gamma coincidence counting rate according to the counting of the digital multipaths;
step 204, calculating according to the beta-gamma coincidence counting rate 18 F nuclide activity concentration.
In the specific implementation, the beta-gamma conforming method is adopted for sampling the gas 18 F, detecting the nuclide activity concentration, and effectively improving the detection efficiency.
The foregoing description is only a preferred embodiment of the present invention, and is not intended to limit the present invention, and any simple modification, variation and equivalent structural changes made to the above embodiment according to the technical substance of the present invention still fall within the scope of the technical solution of the present invention.
Claims (10)
1. A primary loop coolant leakage radiation monitoring system, characterized by: comprises a sampling pipeline (1), a purging pipeline (2) and an exhaust pipeline (3), and an F-18 aerosol detector (4) and an inert gas detector (5); the purging pipeline (2) and the exhaust pipeline (3) are communicated with the sampling pipeline (1), and the F-18 aerosol detector (4) and the inert gas detector (5) are arranged on the sampling pipeline (1);
the sampling pipeline (1) is sequentially provided with a sampling inlet (6), a first stop valve (7), a second stop valve (8), a regulating valve (9), a flowmeter (10), a third stop valve (11) and a fourth stop valve (12) along with the airflow direction, the F-18 aerosol detector (4) is arranged between the second stop valve (8) and the regulating valve (9), the inert gas detector (5) is arranged between the third stop valve (11) and the fourth stop valve (12), and a differential pressure meter (38) is arranged between the inlet and outlet gases of the F-18 aerosol detector (4);
the device is characterized in that a purge inlet (13), a fifth stop valve (14), a one-way valve (15), a sixth stop valve (16), an aerosol and iodine filter (17) and a seventh stop valve (18) are sequentially arranged on the purge pipeline (2) along with the airflow direction, one section of the purge pipeline (2) positioned behind the seventh stop valve (18) is communicated with the sampling pipeline (1), one section of the purge pipeline (2) positioned between the one-way valve (15) and the sixth stop valve (16) is connected with a first connecting pipe (19), and the other end of the first connecting pipe (19) is communicated with one section of the sampling pipeline (1) positioned between the first stop valve (7) and the second stop valve (8);
an eighth stop valve (20), a first sampling pump (21), a ninth stop valve (22), a tenth stop valve (23) and an exhaust port (24) are sequentially arranged on the exhaust pipeline (3) along the airflow direction, the exhaust pipeline (3) is communicated with a section of sampling pipeline (1) positioned behind the fourth stop valve (12), and is communicated with a section of sampling pipeline (1) positioned between the flowmeter (10) and the third stop valve (11) through a second connecting pipe (25); an eleventh stop valve (26), an iodine filter (27) and a twelfth stop valve (28) are sequentially arranged on the second connecting pipe (25) along the airflow direction.
2. The primary loop coolant leakage radiation monitoring system of claim 1, wherein: a third connecting pipe (29) is connected between the air inlet end of the eighth stop valve (20) and the air outlet end of the ninth stop valve (22), and a thirteenth stop valve (30), a second sampling pump (31) and a fourteenth stop valve (32) are sequentially arranged on the third connecting pipe (29) along with the air flow direction.
3. The primary loop coolant leakage radiation monitoring system of claim 2, wherein: the F-18 aerosol detector (4) and the inert gas detector (5) are both arranged in a lead shielding chamber (33).
4. A primary loop coolant leakage radiation monitoring system in accordance with claim 3, wherein: the sampling pipeline (1), the purging pipeline (2), the exhaust pipeline (3), the first sampling pump (21), the second sampling pump (31) and the lead shielding chamber (33) are all installed on the integrated bracket (34).
5. The primary loop coolant leakage radiation monitoring system of claim 4, wherein: and the integrated bracket (34) is also provided with an F-18 aerosol in-situ radiation processor (35), an inert gas in-situ radiation processor (36) and an electric box (37), the F-18 aerosol detector (4) is connected with the F-18 aerosol in-situ radiation processor (35), and the inert gas detector (5) is connected with the inert gas in-situ radiation processor (36).
6. The primary loop coolant leakage radiation monitoring system of claim 1, wherein: the F-18 aerosol detector (4) comprises a shielding shell (4-1), a first cavity (4-2) and a second cavity (4-3) are arranged in the shielding shell (4-1), a beta-sensitive plastic scintillator detector (4-4) used for detecting beta rays emitted by the F-18 aerosol is arranged in the first cavity (4-2), a NaITl detector (4-5) used for detecting gamma rays emitted by the F-18 aerosol is arranged in the second cavity (4-3), a filter paper (4-6) used for sampling the F-18 aerosol is arranged between the beta-sensitive plastic scintillator detector (4-4) and the NaITl detector (4-5), a driving reel (4-7) and a driven reel (4-8) are arranged in the filter paper (4-6), and a sampling part (4-9) is connected between the reel (4-7) and the driven reel (4-8) in a bridging mode, and the sampling part (4-9) is opened between the filter paper (4-5) and the filter paper (4-5) of the filter paper (4-6).
7. A method of monitoring radiation for leakage of a coolant in a circuit employing the system of claim 5, said method comprising the steps of:
step one, sampling gas;
the first stop valve (7) is opened, the second stop valve (8) is opened, the third stop valve (11) is opened, the fourth stop valve (12) is opened, the eighth stop valve (20) is opened, the ninth stop valve (22) is opened and the tenth stop valve (23) is opened, and the fifth stop valve (14) is closed, the sixth stop valve (16) is closed, the seventh stop valve (18) is closed, the eleventh stop valve (26) is closed and the twelfth stop valve (28) is closed; under the action of a first sampling pump (21), gas in the containment sequentially passes through a sampling inlet (6), a first stop valve (7) and a second stop valve (8) to enter an F-18 aerosol detector (4);
step two, F-18 aerosol radiation monitoring;
the F-18 aerosol detector (4) samples the gas 18 F-18 aerosol in situ radiation processor (35) for data processing and display, as 18 F, when the nuclide activity concentration exceeds an alarm threshold, sending an audible and visual alarm signal, and sending the alarm signal to a main control room;
step three, inert gas radiation monitoring;
the sampling gas passing through the F-18 aerosol detector (4) sequentially passes through the regulating valve (9), the flowmeter (10) and the third stop valve (11) to enter the inert gas detector (5); the inert gas detector (5) is used for detecting inert gas in the sampled gas 85 Kr、 133 The method comprises the steps that the total activity concentration of Xe nuclide is detected, a data processing and displaying are carried out by an inert gas in-situ radiation processor (36), and when the activity concentration of the inert gas exceeds an alarm threshold value, an audible and visual alarm signal is sent out and sent to a main control room;
step four, returning the sampling gas;
the sampled gas passing through the inert gas detector (5) sequentially passes through a fourth stop valve (12), an eighth stop valve (20), a first sampling pump (21), a ninth stop valve (22), a tenth stop valve (23) and an exhaust port (24) to return into the containment vessel.
8. The primary loop coolant leakage radiation monitoring method of claim 7, wherein: in the first to fourth steps, when the F-18 aerosol detector (4) fails or filter paper needs to be replaced, the second stop valve (8) is closed, the sixth stop valve (16) is opened, the seventh stop valve (18) is closed, and the sampling gas flows through the aerosol and iodine filter (17) and then enters the inert gas detector (5); when the inert gas detector (5) fails or filter paper needs to be replaced, the third stop valve (11) and the fourth stop valve (12) are closed, the eleventh stop valve (26) and the twelfth stop valve (28) are opened, and sampling gas flows through the iodine filter (27).
9. The primary loop coolant leakage radiation monitoring method of claim 7, wherein: when the sampling monitoring is finished and the purging needs to be carried out, the first stop valve (7) is closed, the fifth stop valve (14) is opened, and the purging gas sequentially enters the sampling pipeline (1) through the purging inlet (13), the fifth stop valve (14) and the one-way valve (15) to be purged and is discharged through the exhaust pipeline (3).
10. The method of monitoring radiation of leakage of coolant in a circuit according to claim 7, wherein in step two said F-18 aerosol detector (4) is used to sample the gas 18 The specific process for detecting the F nuclide activity concentration comprises the following steps:
step 201, monitoring beta+ particle rays emitted by decay of F-18, and counting;
step 202, monitoring gamma photon rays emitted by decay of F-18, and counting;
step 203, calculating to obtain a beta-gamma coincidence counting rate according to the counting of the digital multipaths;
step 204, calculating according to the beta-gamma coincidence counting rate 18 F nuclide activity concentration.
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