CN220960806U - Sampling device for radioactive gas of nuclear power plant - Google Patents
Sampling device for radioactive gas of nuclear power plant Download PDFInfo
- Publication number
- CN220960806U CN220960806U CN202322435746.2U CN202322435746U CN220960806U CN 220960806 U CN220960806 U CN 220960806U CN 202322435746 U CN202322435746 U CN 202322435746U CN 220960806 U CN220960806 U CN 220960806U
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- Prior art keywords
- sampling
- nuclear power
- sampling device
- radioactive
- gas
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- 238000005070 sampling Methods 0.000 title claims abstract description 77
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 34
- 238000002955 isolation Methods 0.000 claims abstract description 10
- 238000003466 welding Methods 0.000 claims description 3
- 239000007789 gas Substances 0.000 claims 10
- 238000003904 radioactive pollution Methods 0.000 abstract description 3
- 230000001788 irregular Effects 0.000 abstract description 2
- 230000002000 scavenging effect Effects 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000000243 solution Substances 0.000 description 2
- 208000019155 Radiation injury Diseases 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 210000001503 joint Anatomy 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 238000010926 purge Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 239000012498 ultrapure water Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Sampling And Sample Adjustment (AREA)
Abstract
The utility model provides a sampling device for radioactive gas in a nuclear power plant, which comprises a rubber hose, an adapter, a female quick connector, a male quick connector and a sampling pipeline which are sequentially connected, wherein a sampling needle cylinder is inserted into the rubber hose for sampling, and a sampling isolation valve is arranged on the sampling pipeline. The sampling device is used for sampling the covering gas of the nuclear power plant, the original sampling pipeline is changed little, the irregular emission of radioactive gas is reduced, the influence of residual gas of an air bag on an analysis result is avoided, and the radioactive inhalation risk of sampling personnel and the radioactive pollution risk of surrounding equipment which are possibly caused are reduced.
Description
Technical Field
The utility model relates to the technical field of radioactive gas sampling in a nuclear power plant, in particular to a sampling device for radioactive gas in the nuclear power plant.
Background
The nuclear power plant has a plurality of systems which are covered by gas, fast neutrons generated by the nuclear reaction need to be moderated into thermal neutrons through high-purity water to maintain the chain reaction, the process can lead to water to be decomposed to generate radioactive gas, and the gas is partially covered by the covering gas according to the Henry law, so that the system covering gas has certain radioactivity. In order to monitor the gas composition in the blanket gas, nuclear power plants need to sample the blanket gas of multiple systems, most of which are radioactive. Part of nuclear power plants adopt an air bag to sample the covering gas of the system, but the sampling mode has the following problems: residual gas in an air bag used for sampling is difficult to completely empty, and if the residual gas is not empty, the reliability of the analysis result of a new sample can be affected; in order to empty the residual air in the air bag, the air bag needs to be repeatedly inflated and deflated, and if the discharged radioactive gas is carelessly inhaled into the body, the discharged radioactive gas can cause internal radiation injury to personnel; the air bag is repeatedly inflated and exhausted, and the exhausted radioactive gas is attached to surrounding equipment, so that the surface of the equipment is polluted by radioactivity; the air bag is generally made of rubber, so that the air bag is easy to age and leak air, and analysis data is unreliable; when the air bag is taken back to a laboratory for analysis, the needle cylinder is used for sampling, and sample gas in the air bag is used for scavenging the sample injection needle cylinder, so that the risk of inhalation of radioactive gas by personnel is increased; during sampling, the sampling line needs to purge dead volume of gas in the sampling line through scavenging. When the air bag is used for sampling, the valve is generally directly opened, and radioactive gas in the pipeline is swept into the surrounding environment, so that the inhalation risk and the environmental pollution risk of personnel are increased.
Disclosure of utility model
The utility model aims to provide a sampling device for radioactive gas in a nuclear power plant, which solves the problems of high risk of people inhaling the radioactive gas, inaccurate data and inconvenient sampling during sampling of an air bag, ensures that the sampling work of the radioactive gas is convenient to operate, avoids the risk and improves the accuracy of the data.
In order to achieve the above object, the present utility model provides the following technical solutions:
The utility model provides a sampling device for nuclear power plant radioactive gas, includes rubber hose, adapter, female quick-operation joint, public quick-operation joint and the sampling pipeline that connects gradually, and the sample cylinder is through inserting the rubber hose takes a sample, be equipped with the sample isolation valve on the sampling pipeline.
As an implementation manner, the rubber hose is fixedly connected with the upper end of the adapter through a buckle.
As an embodiment, the female quick connector and the adapter are connected by threads.
As an embodiment, the female quick connector and the adapter are fixedly connected by welding.
As an embodiment, the rubber hose is provided with a hose valve.
As an implementation, the sampling syringe seals the needle by a rubber sheet.
As an implementation mode, two parallel pipelines are connected below the sampling isolation valve, and each pipeline is provided with a valve.
As an embodiment, the axial dimension of the female quick connector is 6.33cm, and the maximum outer diameter is 2cm.
As an embodiment, the axial dimension of the adapter is 1.5cm, and the maximum outer diameter is 1cm.
As an embodiment, the axial dimension of the male quick connector is 2.43cm, and the maximum outer diameter is 1cm.
Compared with the prior art, the sampling device for the radioactive gas in the nuclear power plant has the following beneficial effects:
the sampling device is used for sampling the covering gas of the nuclear power plant, the original sampling pipeline is changed little, the irregular emission of radioactive gas is reduced, the influence of residual gas of an air bag on an analysis result is avoided, and the radioactive inhalation risk of sampling personnel and the radioactive pollution risk of surrounding equipment which are possibly caused are reduced.
By adopting the sampling device, the sample is directly taken into the needle cylinder for instrument analysis sampling, the intermediate links are reduced, the possibility of distortion of analysis results caused by sample transfer is reduced, and the risk of radioactive pollution of laboratory analysts or equipment is avoided.
Drawings
In order to more clearly illustrate the technical solution of the present utility model, the drawings that are used in the technical description will be briefly described below.
Fig. 1 is a schematic structural diagram of a sampling device for radioactive gas in a nuclear power plant according to the present utility model.
Reference numerals illustrate:
1. A female quick connector; 2. an adapter; 3. a buckle; 4. a sampling needle cylinder; 5. a male quick connector; 6. a sampling line; 7. a hose valve; 8. a rubber hose; 9. sampling isolation valve.
Detailed Description
Further details are provided below with reference to the specific embodiments.
As shown in fig. 1, the present utility model provides a sampling device for radioactive gas in a nuclear power plant, comprising a sampling line 6 leading from the system, a female quick connector 1, a male quick connector 5, an adapter 2, a rubber hose 8, and a sampling syringe 4 (sampling injector). The female quick connector 1, the adapter 2, the rubber hose 8 and the sampling buckle 3 are connected to form a female quick connector sampling component.
The male quick connector 5 is connected above the sampling pipeline 6, and the male quick connector 5 is used for connecting the female quick connector 1.
Preferably, the female quick connector 1 and the adapter 2 are screwed.
Optionally, the female quick connector 1 and the adapter 2 are fixedly connected by welding.
The axial dimension of the female quick connector 1 is 2.33cm, and the maximum outer diameter is 0.74cm.
The axial dimension of the male quick connector 5 is 2.43cm, and the maximum outer diameter is 1.00cm.
The axial dimension of the adapter 2 is 1.5cm and the maximum outer diameter is 1.00cm.
When the sizes of the rubber hose 8 and the adapter 2 are not matched, namely, the rubber hose 8 is sleeved on the adapter 2 and is easy to loosen, a sampling buckle 3 is added, and the rubber hose 8 is fastened on the adapter 2 by the sampling buckle 3.
At least one hose valve 7 is provided on the rubber hose 8, and the flow of gas is controlled by the hose valve 7.
The sampling pipeline 6 is provided with a sampling isolation valve 9, two pipelines connected in parallel are connected below the sampling isolation valve 9, and each pipeline is provided with a valve.
Before sampling, the female quick connector sampling component is in butt joint with the male quick connector 5 on the sampling pipeline 6, the other end of the rubber hose is put into an exhaust system, and the exhaust system is arranged below the drawing of fig. 1. The gas flow direction is from the lower side to the upper side in fig. 1.
During sampling, a sampling isolation valve 9 on a sampling pipeline 6 is opened to scavenge the sampling pipeline, then a needle head of a sampling needle cylinder 4 is pricked into a rubber hose 8, the needle cylinder core rod is pulled back and forth to scavenge the sampling gas, and after the needle cylinder scavenging is finished, the radioactive gas is sampled.
After sampling, the needle is pulled out, the needle is sealed by a rubber sheet, the sampling isolation valve 9 is closed, the female quick connector 1 is pulled out, and the sample in the syringe and the female quick connector sampling component are brought back to the laboratory.
The foregoing is merely illustrative of the present utility model, and the present utility model is not limited thereto, and any changes or substitutions easily contemplated by those skilled in the art within the scope of the present utility model should be included in the scope of the present utility model. Therefore, the protection scope of the present utility model shall be subject to the protection scope of the claims.
Claims (10)
1. A sampling device for nuclear power plant radioactive gas, its characterized in that, including rubber hose (8), adapter (2), female quick-operation joint (1), public quick-operation joint (5) and sample pipeline (6) that connect gradually, sample cylinder (4) are through inserting rubber hose (8) take a sample, be equipped with sample isolation valve (9) on sample pipeline (6).
2. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the rubber hose (8) and the upper end of the adapter (2) are fixedly connected by means of a buckle (3).
3. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the female quick connector (1) and the adapter (2) are connected by means of threads.
4. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the female quick connector (1) and the adapter (2) are fixedly connected by welding.
5. The sampling device for radioactive gas of a nuclear power plant according to claim 1, characterized in that the rubber hose (8) is provided with a hose valve (7).
6. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the sampling needle cylinder (4) seals the needle by means of a rubber sheet.
7. The sampling device for radioactive gas of a nuclear power plant according to claim 1, characterized in that two parallel pipelines are connected below the sampling isolation valve (9), each pipeline being provided with a valve.
8. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the axial dimension of the female quick connector (1) is 6.33cm, the maximum external diameter is 2cm.
9. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the axial dimension of the adapter (2) is 1.5cm, the maximum external diameter being 1cm.
10. The sampling device for radioactive gases of nuclear power plants according to claim 1, characterized in that the male quick connector (5) has an axial dimension of 2.43cm and a maximum external diameter of 1cm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202322435746.2U CN220960806U (en) | 2023-09-07 | 2023-09-07 | Sampling device for radioactive gas of nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202322435746.2U CN220960806U (en) | 2023-09-07 | 2023-09-07 | Sampling device for radioactive gas of nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN220960806U true CN220960806U (en) | 2024-05-14 |
Family
ID=90974055
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202322435746.2U Active CN220960806U (en) | 2023-09-07 | 2023-09-07 | Sampling device for radioactive gas of nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN220960806U (en) |
-
2023
- 2023-09-07 CN CN202322435746.2U patent/CN220960806U/en active Active
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