CN220019462U - Oxyhydrogen content sampling and monitoring device in radioactive gas for nuclear power station - Google Patents
Oxyhydrogen content sampling and monitoring device in radioactive gas for nuclear power station Download PDFInfo
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- CN220019462U CN220019462U CN202320956909.9U CN202320956909U CN220019462U CN 220019462 U CN220019462 U CN 220019462U CN 202320956909 U CN202320956909 U CN 202320956909U CN 220019462 U CN220019462 U CN 220019462U
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- 238000005070 sampling Methods 0.000 title claims abstract description 39
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 27
- 238000012806 monitoring device Methods 0.000 title claims abstract description 10
- 238000001514 detection method Methods 0.000 claims abstract description 25
- 238000005259 measurement Methods 0.000 claims abstract description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 12
- 239000007789 gas Substances 0.000 claims description 76
- 239000001257 hydrogen Substances 0.000 claims description 16
- 229910052739 hydrogen Inorganic materials 0.000 claims description 16
- 238000012544 monitoring process Methods 0.000 claims description 16
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 15
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 12
- 239000001301 oxygen Substances 0.000 claims description 12
- 229910052760 oxygen Inorganic materials 0.000 claims description 12
- 238000006243 chemical reaction Methods 0.000 claims description 10
- 239000003792 electrolyte Substances 0.000 claims description 10
- 238000011084 recovery Methods 0.000 claims description 10
- 238000007789 sealing Methods 0.000 claims description 6
- 238000004458 analytical method Methods 0.000 abstract description 5
- 238000012360 testing method Methods 0.000 description 7
- 238000000034 method Methods 0.000 description 6
- 229910000831 Steel Inorganic materials 0.000 description 4
- 238000004817 gas chromatography Methods 0.000 description 4
- 239000010959 steel Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000004880 explosion Methods 0.000 description 3
- 239000002912 waste gas Substances 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000012159 carrier gas Substances 0.000 description 2
- 230000007547 defect Effects 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 239000003517 fume Substances 0.000 description 1
- 150000002431 hydrogen Chemical class 0.000 description 1
- 210000001503 joint Anatomy 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000004224 protection Effects 0.000 description 1
- 230000001950 radioprotection Effects 0.000 description 1
- 238000006479 redox reaction Methods 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 239000003381 stabilizer Substances 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The utility model provides a sampling and monitoring device for oxyhydrogen content in radioactive gas of a nuclear power station, which comprises an air inlet connected with gas to be sampled, wherein the air inlet is connected with a gas-water separator through a switchable air inlet valve; the top end of the gas-water separator is respectively communicated with a pressure reducing valve and a bypass valve which can be opened and closed through a first three-way valve, the pressure reducing valve and the bypass valve form a detection loop through a second three-way valve, one end of the second three-way valve is communicated with a detection port through a detection valve, and the detection port is communicated with a sensing air inlet of a sensing device; the sensing air outlet of the sensing device is communicated with the collecting port, the collecting port is respectively communicated with the recovering port and the switchable blow-down valve through a third three-way valve, and the blow-down valve is also communicated with the bottom end of the gas-water separator. The utility model directly uses the connecting hose to connect the measuring device with the sampling pipeline of the container to be measured for online measurement, and the device does not need to be transferred to a laboratory for analysis after sampling and does not need to extract a gas sample in advance.
Description
Technical Field
The utility model relates to the technical field of detection of chemical components of electronic products, in particular to a sampling and monitoring device for oxyhydrogen content in radioactive gas of a nuclear power station.
Background
At present, the nuclear power station regularly samples and analyzes the oxyhydrogen content of radioactive gases such as an exhaust gas receiving box and the like every week, which is the requirement of the chemical and radiochemical technical Specification of the nuclear power station. The monitoring is realized by adopting a mode of collecting gas on site and then transferring to laboratory analysis, the monitoring method has higher industrial safety and radiation protection risks, and the risks of triggering the radiation monitoring instrument to give an alarm and even causing irradiation and hydrogen explosion in personnel are generated in the sampling and discharging process. Therefore, a portable sampling and measuring device needs to be developed, the method for monitoring the oxyhydrogen content in the radioactive gas in the past is changed, and the on-site collection of the gas and the high-risk operation accompanied in the transportation process of the gas are avoided, so that the hydrogen and oxygen content in the radioactive gas is safely, quickly and accurately monitored, and the uncontrollable emission of the radioactive gas, hydrogen explosion and personnel internal irradiation risks are reduced. On the other hand, the previous method for monitoring the oxyhydrogen content in the radioactive gas uses steel charges to collect the gas and then transfer the gas to gas chromatography for measurement, so that the price of measuring instruments and equipment is high, and the cost for monitoring the oxyhydrogen content in the radioactive gas is excessive. The newly developed portable sampling and measuring device has the functions of sampling and analyzing, and the cost is less than one quarter of the original equipment.
The receiving systems of nuclear power plant radioactive gas generally fall into two categories: one type is a TEG exhaust gas receiving system; one type is a system for receiving gas generation by various systems such as a pressure stabilizer ring pipe, a main loop system pressure relief box and the like.
In order to prevent the possibility of hydrogen explosion of each gas receiving system, the nuclear power station regularly performs sampling measurement of the hydrogen and oxygen content of the gas receiving tanks at present. The gas of the gas receiving tanks can be sampled in a sampling fume hood through a sampling pipeline of a sampling system. The gas of the gas receiving tank to be tested is introduced into the steel bullet through the quick connector hose, and then is discharged from the steel bullet outlet through the quick connector hose to the waste gas receiving box (such as a TEG head box) with relatively low downstream pressure. And after the sampling is finished, the valve is closed, and then the gas in the steel bomb is transported to a laboratory for gas chromatography analysis. The waste gases collected by these systems, due to the radioactive gases and hydrogen, present significant radioprotection and industrial safety risks during the sampling and monitoring process.
Disclosure of Invention
The utility model aims to provide a sampling and monitoring device for oxyhydrogen content in radioactive gas of a nuclear power station, which solves the technical problem that the sample is directly carried to a sampling point on site without extracting the gas sample in advance and then is connected with a quick connector hose for testing.
In one aspect, a device for sampling and monitoring oxyhydrogen content in a radioactive gas of a nuclear power plant is provided, including:
the gas inlet is connected with the gas to be sampled and is connected with the gas-water separator through a switchable gas inlet valve;
the top end of the gas-water separator is respectively communicated with a pressure reducing valve and a bypass valve which can be opened and closed through a first three-way valve, the pressure reducing valve and the bypass valve form a detection loop through a second three-way valve, one end of the second three-way valve is communicated with a detection port through a detection valve, and the detection port is communicated with a sensing air inlet of a sensing device;
the sensing air outlet of the sensing device is communicated with the collecting port, the collecting port is respectively communicated with the recovering port and the switchable blow-down valve through a third three-way valve, and the blow-down valve is also communicated with the bottom end of the gas-water separator.
Preferably, the sensing device comprises at least a hydrogen measuring sensor and an oxygen measuring sensor; the hydrogen measuring sensor is a thermal conductivity sensor, and the oxygen measuring sensor is an electrochemical sensor.
Preferably, the hydrogen measurement sensor is disposed in a preset thermal conductivity cell, and measures a gas concentration of the gas to be sampled when the gas to be sampled enters the thermal conductivity cell.
Preferably, at least two reaction electrodes and at least one reference electrode are arranged in the oxygen measurement sensor, the reaction electrodes and the reference electrode are arranged in a preset electrolyte, and when the gas to be sampled enters the electrolyte, the gas concentration in the electrolyte is measured.
Preferably, the air inlet valve, the bypass valve, the blow-down valve and the detection valve are respectively provided with corresponding rotary switches.
Preferably, the air inlet, the recovery port, the collection port and the detection port are respectively provided with corresponding self-sealing quick connectors.
Preferably, the recovery port is sequentially connected with the corresponding switch valve and the waste gas receiving box through the self-sealing quick plug connector on the recovery port.
Preferably, the pressure reducing valve is further provided with a corresponding barometer.
In summary, the embodiment of the utility model has the following beneficial effects:
the sampling monitoring device for the oxyhydrogen content in the radioactive gas of the nuclear power station provided by the utility model directly uses the connecting hose to connect the measuring device with the sampling pipeline of the container to be measured for online measurement, and the measuring device does not need to be transferred to a laboratory for analysis after sampling. The defect of gas chromatography is overcome, and the gas sample is not required to be extracted in advance, and the gas sample is directly carried to a sampling point on site to be connected with a quick joint hose for testing; the rechargeable battery is adopted for power supply, the volume is small, the weight is light, the operation is simple, the reaction is rapid, and the reading is stable.
Drawings
In order to more clearly illustrate the embodiments of the utility model or the technical solutions of the prior art, the drawings which are required in the description of the embodiments or the prior art will be briefly described, it being obvious that the drawings in the description below are only some embodiments of the utility model, and that it is within the scope of the utility model to one skilled in the art to obtain other drawings from these drawings without inventive faculty.
Fig. 1 is a schematic diagram of a device for sampling and monitoring oxyhydrogen content in radioactive gas for a nuclear power plant according to an embodiment of the present utility model.
Fig. 2 is a schematic diagram of a device for sampling and monitoring oxyhydrogen content in radioactive gas for a nuclear power plant according to an embodiment of the present utility model.
Detailed Description
The present utility model will be described in further detail with reference to the accompanying drawings, for the purpose of making the objects, technical solutions and advantages of the present utility model more apparent.
Referring to fig. 1 and 2, schematic diagrams of an embodiment of a device for sampling and monitoring oxyhydrogen content in a radioactive gas of a nuclear power plant according to the present utility model are shown. In this embodiment, the apparatus comprises:
an air inlet 1 connected with the air 17 to be sampled, wherein the air inlet 1 is communicated with the air-water separator 3 through an air inlet valve 2 which can be opened and closed;
the top end of the gas-water separator 3 is respectively communicated with a pressure reducing valve 5 and a bypass valve 6 which can be opened and closed through a first three-way valve 4, the pressure reducing valve 5 and the bypass valve 6 form a detection loop through a second three-way valve 7, one end of the second three-way valve 7 is communicated with a detection port 9 through a detection valve 8, and the detection port 9 is communicated with a sensing air inlet 11 of a sensing device 10;
the sensing air outlet 12 of the sensing device 10 is communicated with the collecting port 13, the collecting port 13 is respectively communicated with the recovering port 15 and the switchable blow-down valve 16 through the third three-way valve 14, and the blow-down valve 16 is also communicated with the bottom end of the gas-water separator 3. That is, the device is self-calibrated after being electrified (a ventilation test is performed after ten minutes), the process can eliminate the influence of the ambient temperature, so that the instrument reaches the optimal test state, and other preparation work before the test can be performed at the moment; closing the instrument flow regulating valve, and arranging an air inlet valve 2, a detection valve 8, a bypass valve 6, a blow-down valve 16 and a pressure reducing valve 5 so that all the valves are in a closed state; as shown in fig. 2, the instrument air inlet 1 is connected with the device detection port 9, the instrument air outlet is connected with the device collection port 13, the device air inlet 1 is connected with the sampling port of the sampling gas 17, and the device recovery port 15 is connected with the sampling port of the gas recovery device; after the gas circuit and the instrument are in butt joint and communicated, the air inlet valve 2 of the device is slowly opened, the drain valve 16 is slowly opened after about 1 minute, the pre-exhaust is carried out for about 1 minute, no liquid flows out after flowing out again, and the drain valve 16 is closed.
In a specific embodiment, the sensing device 10 includes at least a hydrogen measurement sensor and an oxygen measurement sensor; the hydrogen measuring sensor is a thermal conductivity sensor, and the oxygen measuring sensor is an electrochemical sensor. The hydrogen measurement sensor is arranged in a preset thermal conductivity cell, and measures the gas concentration of the gas to be sampled 17 when the gas to be sampled 17 enters the thermal conductivity cell. At least two reaction electrodes and at least one reference electrode are arranged in the oxygen measurement sensor, the reaction electrodes and the reference electrode are arranged in a preset electrolyte, and when the gas 17 to be sampled enters the electrolyte, the gas concentration in the electrolyte is measured. That is, the oxygen measurement sensor is an electrochemical sensor: two reaction electrodes (working electrode and counter electrode) and a reference electrode are placed in a specific electrolyte, then voltage is applied to the reaction electrodes, so that the gas to be detected passing through the capillary diffusion grid is subjected to oxidation-reduction reaction, then the current generated during gas electrolysis is measured through a circuit system in the instrument, and then the microprocessor calculates the gas concentration. The hydrogen measurement sensor is a thermal conductivity sensor: when various components and carrier gas pass through the heat conducting pool, if the gas composition and concentration change, different heat is taken away from the thermosensitive element, so that the resistance value of the thermosensitive element changes, and the output signal of the bridge is changed, wherein the size of the signal is in direct proportion to the concentration of the components in the carrier gas.
In this embodiment, the intake valve 2, the bypass valve 6, the drain valve 16, and the detection valve 8 are provided with corresponding rotary switches, respectively. The closing and opening operations can be performed at any time. Corresponding self-sealing quick connectors are respectively arranged on the air inlet 1, the recovery port 15, the collection port 13 and the detection port 9. And various corresponding devices are conveniently connected. The recovery port 15 is sequentially connected with a corresponding switch valve and an exhaust gas receiving box 18 through a self-sealing quick plug connector on the recovery port. The pressure reducing valve 5 is also provided with a corresponding barometer. When the pressure is measured, whether the main table of the pressure reducing valve 5 is displayed or not is checked, if the pressure is more than 0.1Mpa, the pressure reducing valve 5 is adjusted, the auxiliary table of the pressure reducing valve 5 is used, the display is between 0.05 and 0.1, and if the main table of the pressure reducing valve 5 is smaller than 0.1Mpa, the bypass valve 6 is directly opened. After the instrument is self-calibrated, opening an instrument flow regulating valve to regulate the flow to 0.3-0.45L/min; after 2-3 minutes of data stabilization, the measurement is completed, the current data can be saved by clicking a data saving key, and the current test state can be displayed by clicking a curve display key by measuring the data in a curve mode; after the measurement of the instrument is completed, the air inlet valve 2 is closed firstly, then other valves are closed, the connecting pipe of the air inlet and outlet of the instrument is taken down, and the instrument is closed.
In summary, the embodiment of the utility model has the following beneficial effects:
the sampling monitoring device for the oxyhydrogen content in the radioactive gas of the nuclear power station provided by the utility model directly uses the connecting hose to connect the measuring device with the sampling pipeline of the container to be measured for online measurement, and the measuring device does not need to be transferred to a laboratory for analysis after sampling. The defect of gas chromatography is overcome, and the gas sample is not required to be extracted in advance, and the gas sample is directly carried to a sampling point on site to be connected with a quick joint hose for testing; the rechargeable battery is adopted for power supply, the volume is small, the weight is light, the operation is simple, the reaction is rapid, and the reading is stable.
The foregoing disclosure is illustrative of the present utility model and is not to be construed as limiting the scope of the utility model, which is defined by the appended claims.
Claims (8)
1. A oxyhydrogen content sampling monitoring device in radioactive gas for nuclear power station, characterized by comprising:
the gas inlet is connected with the gas to be sampled and is connected with the gas-water separator through a switchable gas inlet valve;
the top end of the gas-water separator is respectively communicated with a pressure reducing valve and a bypass valve which can be opened and closed through a first three-way valve, the pressure reducing valve and the bypass valve form a detection loop through a second three-way valve, one end of the second three-way valve is communicated with a detection port through a detection valve, and the detection port is communicated with a sensing air inlet of a sensing device;
the sensing air outlet of the sensing device is communicated with the collecting port, the collecting port is respectively communicated with the recovering port and the switchable blow-down valve through a third three-way valve, and the blow-down valve is also communicated with the bottom end of the gas-water separator.
2. The sampling monitoring device for oxyhydrogen content in radioactive gas of nuclear power plant according to claim 1, wherein the sensing device comprises at least a hydrogen measuring sensor and an oxygen measuring sensor; the hydrogen measuring sensor is a thermal conductivity sensor, and the oxygen measuring sensor is an electrochemical sensor.
3. The apparatus for monitoring the oxyhydrogen content in a radioactive gas for a nuclear power plant according to claim 2, wherein the hydrogen measurement sensor is disposed in a predetermined thermal conductivity cell, and measures a gas concentration of the gas to be sampled when the gas to be sampled enters the thermal conductivity cell.
4. The apparatus for monitoring the sampling of the oxyhydrogen content in a radioactive gas for a nuclear power plant according to claim 3, wherein at least two reaction electrodes and at least one reference electrode are disposed in the oxygen measurement sensor, the reaction electrodes and the reference electrode are disposed in a predetermined electrolyte, and when the gas to be sampled enters the electrolyte, the gas concentration in the electrolyte is measured.
5. The apparatus for monitoring the oxyhydrogen content in a radioactive gas for a nuclear power plant according to claim 4, wherein corresponding rotary switches are respectively provided on the intake valve, the bypass valve, the blow-down valve and the detection valve.
6. The device for sampling and monitoring the oxyhydrogen content in the radioactive gas of the nuclear power plant according to claim 5, wherein the gas inlet, the recovery port, the collection port and the detection port are respectively provided with corresponding self-sealing quick connectors.
7. The sampling and monitoring device for oxyhydrogen content in radioactive gas in a nuclear power plant according to claim 6, wherein the recovery port is sequentially connected with a corresponding switch valve and an exhaust gas receiving tank through a self-sealing quick connector thereon.
8. The device for sampling and monitoring the oxyhydrogen content in the radioactive gas of the nuclear power plant according to claim 1, wherein a corresponding barometer is further arranged on the pressure reducing valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320956909.9U CN220019462U (en) | 2023-04-25 | 2023-04-25 | Oxyhydrogen content sampling and monitoring device in radioactive gas for nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320956909.9U CN220019462U (en) | 2023-04-25 | 2023-04-25 | Oxyhydrogen content sampling and monitoring device in radioactive gas for nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN220019462U true CN220019462U (en) | 2023-11-14 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320956909.9U Active CN220019462U (en) | 2023-04-25 | 2023-04-25 | Oxyhydrogen content sampling and monitoring device in radioactive gas for nuclear power station |
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| Country | Link |
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| CN (1) | CN220019462U (en) |
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2023
- 2023-04-25 CN CN202320956909.9U patent/CN220019462U/en active Active
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