CN219832204U - Hand protection device in radioactive liquid sampling and inspection process - Google Patents
Hand protection device in radioactive liquid sampling and inspection process Download PDFInfo
- Publication number
- CN219832204U CN219832204U CN202320803426.5U CN202320803426U CN219832204U CN 219832204 U CN219832204 U CN 219832204U CN 202320803426 U CN202320803426 U CN 202320803426U CN 219832204 U CN219832204 U CN 219832204U
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- cap
- lead
- raw material
- lead tank
- top cover
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- 238000005070 sampling Methods 0.000 title claims abstract description 46
- 238000000034 method Methods 0.000 title claims abstract description 28
- 230000002285 radioactive effect Effects 0.000 title claims abstract description 27
- 239000007788 liquid Substances 0.000 title claims abstract description 23
- 238000007689 inspection Methods 0.000 title claims abstract description 19
- 239000002994 raw material Substances 0.000 claims abstract description 53
- 239000010935 stainless steel Substances 0.000 claims description 33
- 229910001220 stainless steel Inorganic materials 0.000 claims description 33
- 238000012360 testing method Methods 0.000 claims description 9
- 239000000463 material Substances 0.000 claims description 8
- 229920003023 plastic Polymers 0.000 claims description 5
- 239000004033 plastic Substances 0.000 claims description 5
- 229910000831 Steel Inorganic materials 0.000 claims description 3
- 229910001215 Te alloy Inorganic materials 0.000 claims description 3
- 239000010959 steel Substances 0.000 claims description 3
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 claims description 3
- 229910052721 tungsten Inorganic materials 0.000 claims description 3
- 239000010937 tungsten Substances 0.000 claims description 3
- -1 but not limited to Substances 0.000 claims 2
- 230000005855 radiation Effects 0.000 abstract description 7
- 239000000443 aerosol Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 229910000619 316 stainless steel Inorganic materials 0.000 description 1
- 229930182555 Penicillin Natural products 0.000 description 1
- JGSARLDLIJGVTE-MBNYWOFBSA-N Penicillin G Chemical compound N([C@H]1[C@H]2SC([C@@H](N2C1=O)C(O)=O)(C)C)C(=O)CC1=CC=CC=C1 JGSARLDLIJGVTE-MBNYWOFBSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229940049954 penicillin Drugs 0.000 description 1
Landscapes
- Sampling And Sample Adjustment (AREA)
Abstract
The utility model discloses a hand protection device in the radioactive liquid sampling and inspection process, which comprises a lead tank cap and a shielding top cover detachably arranged on the lead tank cap; the lead tank cap is covered on the lead tank body, and a vertical through hole is arranged at the top of the lead tank cap corresponding to the bottle opening of the raw material bottle in the lead tank body; the shielding top cover is provided with a guide groove corresponding to the vertical through hole, the bottom of the guide groove is communicated with the guide needle tube in the vertical direction, and the needle head end of the guide needle tube penetrates through the vertical through hole and extends out of the lead pot cap for a distance, so that the needle head end of the guide needle tube penetrates through the bottle cap of the raw material bottle and then is inserted into the raw material bottle. In the whole sampling and inspection process, the raw material bottle is always kept in the lead tank, and meanwhile, the shielding top cover is additionally arranged on the raw material bottle and the hands of an operator, so that the condition that the hands are directly exposed above the raw material bottle is avoided when the operator does the operation, the purpose of reducing the irradiation radiation level outside the hands of the operator and the working position is achieved, the operation procedure is simplified, and the effective working time is shortened.
Description
Technical Field
The utility model relates to the technical field of radiation protection application, in particular to a hand protection device in the radioactive liquid sampling and inspection process.
Background
In the process of inspection and sampling, particularly for the inspection and sampling of radioactive samples, the raw material bottle containing the radioactive samples is usually required to be taken out from the lead tank, the aluminum cover of the raw material bottle is opened, and the capillary tube is inserted into the raw material bottle for sampling operation, in the whole sampling process, the radiation level of the working position of an operator is higher because the hand of the operator is directly exposed above the raw material bottle, particularly the average radiation level of the hand is 4-5msv/h and can reach 6.5msv/h, and the mode of opening the cover is also very easy to cause aerosol pollution of a laboratory, so that a hand protection device in the process of sampling and testing radioactive liquid is needed.
Disclosure of Invention
Aiming at the defects in the prior art, the utility model provides a hand protection device in the radioactive liquid sampling and inspection process.
The utility model discloses a hand protection device in the radioactive liquid sampling and inspection process, which comprises a lead tank cap and a shielding top cover detachably arranged above the lead tank cap;
the lead tank cap is used for being covered on the lead tank body, and a vertical through hole is formed in the top of the lead tank cap corresponding to the bottle opening of the raw material bottle in the lead tank body;
the shielding top cover is provided with a guide groove corresponding to the position of the vertical through hole, the bottom of the guide groove is communicated with the guide needle tube in the vertical direction, and the needle head end of the guide needle tube penetrates through the vertical through hole and stretches out of the lead pot cap for a certain distance, so that the needle head end of the guide needle tube penetrates through the bottle cap of the raw material bottle and then is inserted into the raw material bottle.
As a further improvement of the utility model, the outer diameter of the lead tank cap is consistent with the outer diameter of the lead tank body.
As a further improvement of the utility model, the shielding top cover is a circular stainless steel top cover, and the top of the circular stainless steel top cover is upwards raised near the center of a circle to form a boss;
and a guide groove is formed in the boss at a position corresponding to the vertical through hole, and the bottom of the guide groove is communicated with the guide needle tube.
As a further improvement of the present utility model, the guide groove includes, but is not limited to, an inverted cone guide groove.
As a further improvement of the utility model, a plurality of first bolt holes are annularly distributed on the outer circumference of the circular stainless steel top cover, and a plurality of second bolt holes are arranged at the top of the lead tank cap corresponding to the positions of the plurality of first bolt holes;
bolts sequentially penetrate through the first bolt holes and the second bolt holes to finish connection of the round stainless steel top cover and the lead tank cap.
As a further improvement of the utility model, the outer diameter of the circular stainless steel top cover is identical to the outer diameter of the lead tank cap.
As a further improvement of the utility model, after the lead pot cap with the shielding top cover is arranged on the lead pot body, the needle end of the guide needle tube passes through the bottle cap of the raw material bottle and is inserted into the raw material bottle;
the capillary tube for sampling sequentially passes through the guide groove and the guide needle tube from top to bottom and then is placed in the raw material bottle for sampling.
As a further improvement of the present utility model, the guide needle tube has an inner diameter larger than an outer diameter of the sampling capillary tube.
As a further improvement of the utility model, the materials of the lead tank cap comprise, but are not limited to, tungsten steel, lead tellurium alloy and 316L stainless steel.
As a further improvement of the utility model, the materials of the guide needle tube comprise, but are not limited to, stainless steel and plastics.
Compared with the prior art, the utility model has the beneficial effects that:
according to the utility model, the lead tank cap is improved, the shielding top cover and the guide needle tube are additionally arranged, so that the raw material bottle is always kept in the lead tank in the whole sampling and inspection process, meanwhile, the shielding top cover is additionally arranged on the raw material bottle and the hands of an operator, so that the condition that the hands are directly exposed above the raw material bottle is avoided when the operator performs the operation, the purpose of reducing the radiation level of personnel at the hands and the outside of a working position is achieved, the risk of aerosol pollution caused by the uncapping operation is effectively reduced, the breaking risk existing in the process of clamping the raw material bottle by forceps is avoided, and the effective working time is shortened while the operation procedure is simplified.
Drawings
FIG. 1 is a schematic view of a hand guard during a radioactive liquid sampling test according to an embodiment of the present utility model;
FIG. 2 is a schematic view of a shielding top cover and a guide tube of a hand protecting device in a radioactive liquid sampling inspection process according to an embodiment of the present utility model;
FIG. 3 is a side cross-sectional view of the shield cap and guide tube structure of the hand guard during a radioactive liquid sampling test according to one embodiment of the present utility model;
FIG. 4 is a schematic view showing the structure of a guiding needle tube of a hand protecting device inserted into a raw material bottle in a radioactive liquid sampling inspection process according to an embodiment of the present utility model;
FIG. 5 is a schematic view of the cooperation of a top shield cover, a lead can cap and a lead can body of a hand protection device in a radioactive liquid sampling inspection process according to an embodiment of the present utility model;
fig. 6 is a schematic view of a hand-held stainless steel support structure of a hand guard during a radioactive liquid sampling test according to an embodiment of the present utility model.
In the figure:
1. a lead can cap; 2. a circular stainless steel top cover; 21. a boss; 22. a guide groove; 23. a first bolt hole; 3. a guide needle tube; 4. a lead tank body; 5. a raw material bottle; 6. a stainless steel bracket; 61. u-shaped notch.
Detailed Description
For the purpose of making the objects, technical solutions and advantages of the embodiments of the present utility model more apparent, the technical solutions of the embodiments of the present utility model will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present utility model, and it is apparent that the described embodiments are some embodiments of the present utility model, but not all embodiments of the present utility model. All other embodiments, which can be made by those skilled in the art based on the embodiments of the utility model without making any inventive effort, are intended to be within the scope of the utility model.
In the description of the present utility model, it should be noted that the directions or positional relationships indicated by the terms "center", "upper", "lower", "left", "right", "vertical", "horizontal", "inner", "outer", etc. are based on the directions or positional relationships shown in the drawings, are merely for convenience of describing the present utility model and simplifying the description, and do not indicate or imply that the devices or elements referred to must have a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present utility model. Furthermore, the terms "first," "second," and "third" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present utility model, it should also be noted that, unless explicitly specified and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be either fixedly connected, detachably connected, or integrally connected, for example; can be mechanically or electrically connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present utility model will be understood in specific cases by those of ordinary skill in the art.
The utility model is described in further detail below with reference to the attached drawing figures:
as shown in fig. 1, the utility model provides a hand protection device in a radioactive liquid sampling and inspection process, which comprises a lead tank cap 1 and a shielding top cover detachably arranged above the lead tank cap 1; the lead tank cap 1 is used for being covered on the lead tank body 4, and a vertical through hole is arranged at the top of the lead tank cap 1 corresponding to the bottleneck position of the raw material bottle 5 in the lead tank body 4; the shielding top cover is provided with a guide groove 22 corresponding to the vertical through hole, the bottom of the guide groove 22 is communicated with the guide needle tube 3 along the vertical direction, and the needle head end of the guide needle tube 3 penetrates through the vertical through hole and extends out of the lead pot cap 1 for a certain distance, so that the needle head end of the guide needle tube 3 penetrates through the bottle cap of the raw material bottle 5 and then is inserted into the raw material bottle 5.
According to the utility model, the lead tank cap 1 is improved, the shielding top cover and the guide needle tube 3 are additionally arranged, so that the raw material bottle 5 is always kept in the lead tank in the whole sampling inspection process, meanwhile, the shielding top cover is additionally arranged on the raw material bottle 5 and the hands of an operator, so that the condition that the hands are directly exposed above the raw material bottle is avoided when the operator performs the operation, the purpose of reducing the radiation level of the hands of the operator and the outside of the working position is achieved, the risk of aerosol pollution caused by the uncapping operation is effectively reduced, the breaking risk existing in the process of clamping the raw material bottle by forceps is avoided, and the effective working time is shortened while the operation procedure is simplified.
Specific:
as shown in fig. 1, the outer diameter of the lead tank cap 1 is identical to the outer diameter of the lead tank body 4, so that the lead tank cap 1 can be completely covered above the lead tank body 4, and the shielding effect of the lead tank cap 1 and the lead tank body 4 on radioactive samples in the raw material bottle 4 is ensured.
As shown in fig. 2-5, the shielding top cover in the utility model is a circular stainless steel top cover 2, and the top of the circular stainless steel top cover 2 is upwards protruded at the position close to the center of a circle to form a boss 21; the boss 21 is provided with a guide groove 22 corresponding to the vertical through hole, and the bottom of the guide groove 22 is communicated with the guide needle tube 3.
Further, the guide slot 22 of the present utility model includes, but is not limited to, an inverted conical guide slot, and other guide structures that achieve the same guiding function may be used.
Further, a plurality of first bolt holes 23 are annularly distributed on the outer circumference of the circular stainless steel top cover 2, and a plurality of second bolt holes are formed in the top of the lead tank cap 1 corresponding to the positions of the plurality of first bolt holes 23; bolts sequentially pass through the first bolt holes 23 and the second bolt holes to finish the connection of the circular stainless steel top cover 2 and the lead tank cap 1.
Further, the outer diameter of the circular stainless steel top cover 2 in the utility model is consistent with the outer diameter of the lead pot cap 1.
Further, the thickness of the circular stainless steel cap 2 in the present utility model is adjusted with the radiation intensity of the radioactive sample stored in the source bottle 5.
Further, in the utility model, after the lead tank cap 1 provided with the shielding top cover is covered on the lead tank body 4, the needle end of the guide needle tube 3 passes through the bottle cap of the raw material bottle 5 and is inserted into the raw material bottle 5; the capillary tube for sampling passes through the guide groove 22 and the guide needle tube 3 in turn from top to bottom and then is placed in the raw material bottle 5 for sampling.
Further, the inner diameter of the guide needle tube 3 is larger than the outer diameter of the sampling capillary tube in the utility model, so that the sampling capillary tube can be penetrated out of the guide needle tube 3, and the sampling capillary tube cannot be broken and damaged due to collision of the guide needle tube 3.
Furthermore, the length of the guide needle tube 3 in the utility model is adjusted according to the depth of the raw material bottle 5, so that after the lead cap cover with the shielding top cover is arranged on the lead tank body 4, the needle end of the guide needle tube 3 can be inserted into the raw material bottle 5, and the sampling capillary tube is convenient for extracting samples in the raw material bottle 5.
Further, the material of the guide needle tube 3 in the present utility model includes, but is not limited to, stainless steel, plastic and other metal tube, and when plastic is selected, the present utility model is preferably food grade plastic tube.
Further, the raw material bottle 5 in the present utility model includes, but is not limited to, penicillin bottles.
Further, the size of the lead tank cap 1 in the utility model is matched with the size of the lead tank body 4 to be sampled.
Further, the material of the lead can cap 1 in the present utility model may vary with the shielding material and structure of the lead can cap 1 according to the type and activity of the radionuclide in the raw material bottle 5, and the material of the lead can cap 1 in the present utility model includes but is not limited to tungsten steel, tellurium alloy and 316L stainless steel.
Furthermore, the lead pot cap 1 and the shielding top cover can be integrally manufactured.
As shown in fig. 6, the utility model further comprises a stainless steel bracket 6 for limiting the movement of the raw material bottle 5, wherein one end of the stainless steel bracket 6 is provided with a U-shaped notch 61 for being clamped in a concave part below the bottle mouth of the raw material bottle 5, and when in actual use, an operator can fix the raw material bottle 5 through the stainless steel bracket 6, so that the direct contact between the hand and the sample bottle is avoided, the operation distance is increased, and the external irradiation level of the hand and the dosage are reduced. The stainless steel bracket 6 can also be used for taking out or placing the raw material bottle 5.
The application method of the utility model comprises the following steps:
1) An operator holds the stainless steel bracket 6 by hand, props against the upper part of the raw material bottle 5 in the lead tank body 4 through a U-shaped notch at the front end of the stainless steel bracket 6, and pulls out the lead tank cap of the lead tank body 4 upwards;
2) An operator covers a lead tank cap 1 with a shielding top cover on a lead tank body 4 from top to bottom, ensures that the needle end at the bottom of a guide needle tube 3 penetrates through a raw material bottle 5 and is arranged in the raw material bottle 5;
3) The operator sequentially passes through the guide groove 22 and the guide needle tube 3 from top to bottom through the capillary tube for sampling, and then is placed in the raw material bottle 5 for sampling;
4) After the sampling is finished, an operator holds the stainless steel bracket 6 by hand, props against the upper part of the raw material bottle 5 in the lead tank body 4 through a U-shaped notch at the front end of the stainless steel bracket 6, upwards pulls out the lead tank cap 1 with the shielding top cover, and re-covers the lead tank body 4 from the lead tank cap, thereby finishing the sampling operation process.
Further, as shown in table 1, the external irradiation level of the working position of the operator is generally reduced after the hand shielding device is arranged, and the specific situations are as follows:
TABLE 1 comparison of dosage conditions experienced by operators before and after improvement
As can be seen from comparison of the two table data, in the improvement process, due to the fact that time protection, shielding protection and distance protection are well applied, the external irradiation level of the working position of the improved staff is greatly reduced compared with that before improvement, the purpose of reducing the dosage of the staff is achieved, and compared with a traditional operation mode, the effective working time is shortened to 4 minutes from 7 minutes.
The above is only a preferred embodiment of the present utility model, and is not intended to limit the present utility model, but various modifications and variations can be made to the present utility model by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present utility model should be included in the protection scope of the present utility model.
Claims (10)
1. The hand protection device in the radioactive liquid sampling and inspection process is characterized by comprising a lead tank cap and a shielding top cover detachably arranged above the lead tank cap;
the lead tank cap is used for being covered on the lead tank body, and a vertical through hole is formed in the top of the lead tank cap corresponding to the bottle opening of the raw material bottle in the lead tank body;
the shielding top cover is provided with a guide groove corresponding to the position of the vertical through hole, the bottom of the guide groove is communicated with the guide needle tube in the vertical direction, and the needle head end of the guide needle tube penetrates through the vertical through hole and stretches out of the lead pot cap for a certain distance, so that the needle head end of the guide needle tube penetrates through the bottle cap of the raw material bottle and then is inserted into the raw material bottle.
2. The hand guard during a radioactive liquid sampling test according to claim 1, wherein the outer diameter of the lead tank cap is identical to the outer diameter of the lead tank body.
3. The hand protection device in the radioactive liquid sampling inspection process according to claim 1, wherein the shielding top cover is a circular stainless steel top cover, and the top of the circular stainless steel top cover is upwards protruded at a position close to the center of a circle to form a boss;
the boss is provided with a guide groove corresponding to the vertical through hole, and the bottom of the guide groove is communicated with the guide needle tube.
4. A hand guard in a radioactive liquid sampling test according to claim 3 wherein the guide grooves include, but are not limited to, inverted cone guide grooves.
5. The hand protection device in the radioactive liquid sampling inspection process according to claim 3, wherein a plurality of first bolt holes are annularly distributed on the outer circumference of the circular stainless steel top cover, and a plurality of second bolt holes are formed at the top of the lead pot cap corresponding to the plurality of first bolt holes;
bolts sequentially penetrate through the first bolt holes and the second bolt holes to finish connection of the round stainless steel top cover and the lead tank cap.
6. A hand guard in a radioactive liquid sampling test process according to claim 3 wherein the outer diameter of the circular stainless steel top cover is identical to the outer diameter of the lead can cap.
7. The hand guard during radioactive liquid sampling inspection according to claim 1, wherein after the lead pot cap with the shield top cover mounted thereon is set on the lead pot body, the needle end of the guide needle tube passes through the bottle cap of the raw material bottle and is inserted into the raw material bottle;
the capillary tube for sampling sequentially passes through the guide groove and the guide needle tube from top to bottom and then is placed in the raw material bottle for sampling.
8. The hand guard during a radioactive liquid sampling test of claim 7, wherein the guide needle tube has an inner diameter greater than an outer diameter of the sampling capillary tube.
9. The hand guard of claim 1, wherein the lead cap comprises a material including, but not limited to, tungsten steel, a lead tellurium alloy, and 316L stainless steel.
10. The hand guard during a radioactive liquid sampling test according to claim 1, wherein the guide needle tube comprises a material including, but not limited to, stainless steel and plastic.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320803426.5U CN219832204U (en) | 2023-04-12 | 2023-04-12 | Hand protection device in radioactive liquid sampling and inspection process |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202320803426.5U CN219832204U (en) | 2023-04-12 | 2023-04-12 | Hand protection device in radioactive liquid sampling and inspection process |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN219832204U true CN219832204U (en) | 2023-10-13 |
Family
ID=88248860
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202320803426.5U Active CN219832204U (en) | 2023-04-12 | 2023-04-12 | Hand protection device in radioactive liquid sampling and inspection process |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN219832204U (en) |
-
2023
- 2023-04-12 CN CN202320803426.5U patent/CN219832204U/en active Active
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