CN210271811U - Neutron source transfer container - Google Patents
Neutron source transfer container Download PDFInfo
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- CN210271811U CN210271811U CN201920776837.3U CN201920776837U CN210271811U CN 210271811 U CN210271811 U CN 210271811U CN 201920776837 U CN201920776837 U CN 201920776837U CN 210271811 U CN210271811 U CN 210271811U
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Abstract
The utility model provides a neutron source shifts container, including hemispherical first casing and hemispherical second casing, two plane mutual lock fixed connection of first casing and second casing, the planar center of first casing is equipped with the bellying, the second casing on be equipped with the recess with the bellying adaptation, the bellying on be equipped with the neutron source standing groove, first casing and second casing are inside hollow structure, first casing and second casing intussuseption are full of neutron shielding material, all are equipped with the release valve of release neutron shielding material on first casing and the second casing, all be equipped with the injection valve of injection neutron shielding material on first casing and the second casing, first casing and second casing make by the material that is convenient for neutron transmission.
Description
Technical Field
The utility model relates to a radioactive substance shifts technical field, concretely relates to neutron source shifts container.
Background
The neutron source obtains neutrons by utilizing the nuclear reaction of α particles emitted by radionuclide decay and neutron-rich nucleins (α, n) or neutrons generated by radionuclide spontaneous fission, has the advantages of long service life, stable neutron emission, moderate volume and the like, is widely applied to various fields of industry, agriculture, medicine and scientific research, particularly is a neutron source for starting nuclear reactors, has the advantage of no substitution, and has more and more demands on the neutron source along with the continuous construction of nuclear power stations.
The external irradiation protection of neutrons is mainly used for shielding fast neutrons, and the interaction between the fast neutrons and substances is mainly elastic scattering and inelastic scattering, so that substances containing much hydrogen, such as water, paraffin, polyethylene and the like, are selected as the shielding materials for the neutrons. The frame structure of the storage and transportation container of the neutron source is carbon steel and paraffin lining, the protective material is paraffin, the carbon steel plays a role in fixing, and the problems of large mass and inconvenient transfer exist.
In addition, the neutron source needs to measure accurate neutron emissivity before use, and the neutron source needs to be transferred from a storage place to a measurement place for measurement in the process, so that the neutron source is troublesome to take and easy to cause radiation accidents, and harm is caused to operators.
SUMMERY OF THE UTILITY MODEL
To the problem pointed out in the background art, the utility model provides a neutron source transfer container convenient to remove, be convenient for carry out the measurement to neutron emissivity.
The technical scheme of the utility model is realized like this:
the utility model provides a neutron source shifts container, includes hemispherical first casing and hemispherical second casing, two mutual lock fixed connection of plane ability of first casing and second casing, the planar center of first casing is equipped with the bellying, the second casing on be equipped with the recess with the bellying adaptation, the bellying on be equipped with the neutron source standing groove, first casing and second casing are inside hollow structure, first casing and second casing intussuseption are full of neutron shielding material, all be equipped with the release valve of release neutron shielding material on first casing and the second casing, all be equipped with the injection valve of injection neutron shielding material on first casing and the second casing, first casing and second casing make by the material of being convenient for neutron transmission.
The utility model discloses still further set up to, first casing and second casing in all fill water, the relief valve for the valve that drains, the filling valve be the water intaking valve.
The utility model discloses still further set up to, first casing and second casing on distribute and have a plurality of through-holes that communicate in it, be equipped with the air bag in first casing and the second casing respectively, the air bag in be full of hydrogen, the relief valve be the bleed valve, bleed valve and the inside intercommunication of air bag, the filling valve be admission valve, admission valve and the inside intercommunication of air bag.
The utility model discloses still further set up to, the plane of first casing and second casing on be equipped with the flange respectively, first casing and second casing pass through flange and screw fixed connection.
The utility model discloses still further set up to, first casing and second casing make by the aluminum product.
The utility model discloses still further set up to, first casing and second casing on be equipped with the handle respectively.
The utility model discloses still further set up to, the second casing be located the downside of first casing, second casing downside is equipped with the base, the second casing passes through the support and is connected with the base, the downside of base is equipped with the gyro wheel.
The utility model has the advantages that:
the utility model provides a neutron source shifts container, it provides a hollow casing of inside and bears neutron source, and pack neutron shielding material in the casing, this neutron shielding material is water or hydrogen, whole transfer container is just lighter like this, be convenient for remove, and neutron shielding material in the casing can convenient injection and release, neutron shielding material in the casing is fallen in the release under certain circumstances makes whole container lighter, because the casing is made by the material of the neutron transmission of being convenient for, after neutron shielding material is fallen in the release like this, the neutron just can be easily come from the casing, when testing neutron source's emissivity like this, just need not take out the neutron, directly take the container together and test, it is more convenient and simple.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings needed to be used in the description of the embodiments or the prior art will be briefly described below, it is obvious that the drawings in the following description are only some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without inventive exercise.
Fig. 1 is a schematic structural view of the present invention;
fig. 2 is a schematic structural diagram of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be described clearly and completely with reference to the accompanying drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
The present invention is described below with reference to fig. 1-2:
the first embodiment is as follows: a neutron source transfer container comprises a hemispherical first shell 10 and a hemispherical second shell 20, wherein two planes of the first shell 10 and the second shell 20 can be mutually buckled and fixedly connected.
The center of the plane of the first shell 10 is provided with a convex part 30, the second shell 20 is provided with a groove 40 matched with the convex part 30, and the convex part 30 is provided with a neutron source placing groove 50.
The first casing 10 and the second casing 20 are filled with water, the release valve 60 is a water drain valve, and the injection valve 70 is a water inlet valve. After the water is filled, the neutron source is wrapped by a thick water layer, and emitted neutrons are shielded and attenuated by the water layer when passing through the water layer. The container can be relatively large, and the volume of the container is designed according to the thickness of a water layer.
Example 2: the structure of the embodiment 2 is basically the same as that of the embodiment 1, except that the neutron shielding material is filled differently, so that some structural changes are brought, a plurality of through holes communicated with the first shell 10 and the second shell 20 are distributed on the first shell 10 and the second shell 20, the first shell 10 and the second shell 20 are respectively provided with an inflatable bag 80, the inflatable bag 80 is filled with hydrogen, the release valve 60 is a deflation valve, the deflation valve is communicated with the inside of the inflatable bag 80, the injection valve 70 is an air inlet valve, and the air inlet valve is communicated with the inside of the inflatable bag 80. Hydrogen is injected into the inflatable bag through the air inlet valve, the inflatable bag expands to expel air in the first shell 10 and the second shell 20, the shape of the inflatable bag is designed to be matched with the inner space of the first shell 10 and the inner space of the second shell 20, and therefore after the inflatable bag is filled with hydrogen, the neutron source located in the middle of the shells is completely covered by a layer of hydrogen, and the shielding effect on emitted neutrons is achieved.
The plane of the first shell 10 and the plane of the second shell 20 are respectively provided with a flange 90, the first shell 10 and the second shell 20 are fixedly connected through the flange 90 and a screw, and the connection structure is simple and convenient to operate.
The first shell 10 and the second shell 20 are made of aluminum materials, so that neutrons can be transmitted conveniently.
The first shell 10 and the second shell 20 are respectively provided with a handle 32, so that when the volume of the container is smaller, the container is convenient to transfer manually.
The second casing 20 is located at the lower side of the first casing 10, a base 12 is arranged at the lower side of the second casing 20, the second casing 20 is connected with the base 12 through a bracket 13, and rollers 14 are arranged at the lower side of the base 12. In the technical scheme, when the volume of the container is larger, the container can be conveniently and easily moved to the trolley.
The utility model has the advantages that:
the utility model provides a neutron source shifts container, it provides a hollow casing of inside and bears neutron source, and pack neutron shielding material in the casing, this neutron shielding material is water or hydrogen, whole transfer container is just lighter like this, be convenient for remove, and neutron shielding material in the casing can convenient injection and release, neutron shielding material in the casing is fallen in the release under certain circumstances makes whole container lighter, because the casing is made by the material of the neutron transmission of being convenient for, after neutron shielding material is fallen in the release like this, the neutron just can be easily come from the casing, when testing neutron source's emissivity like this, just need not take out the neutron, directly take the container together and test, it is more convenient and simple.
The above description is only for the preferred embodiment of the present invention and should not be taken as limiting the invention, and any modifications, equivalent replacements, improvements, etc. made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (7)
1. A neutron source transfer vessel, characterized by: including hemispherical first casing and hemispherical second casing, two mutual lock fixed connection of plane ability of first casing and second casing, the planar center of first casing is equipped with the bellying, the second casing on be equipped with the recess with the bellying adaptation, the bellying on be equipped with the neutron source standing groove, first casing and second casing are inside hollow structure, first casing and second casing intussuseption are full of neutron shielding material, all are equipped with the release valve of release neutron shielding material on first casing and the second casing, all be equipped with the injection valve of injection neutron shielding material on first casing and the second casing, first casing and second casing be made by the neutron transmission's of being convenient for material.
2. A neutron source transfer vessel according to claim 1, wherein: the first shell and the second shell are filled with water, the release valve is a water drain valve, and the injection valve is a water inlet valve.
3. A neutron source transfer vessel according to claim 1, wherein: the hydrogen-filled gas-filled bag is characterized in that a plurality of through holes communicated with the inside of the first shell and the second shell are distributed on the first shell and the second shell, gas-filled bags are respectively arranged in the first shell and the second shell, hydrogen is filled in the gas-filled bags, the release valve is a gas release valve, the gas release valve is communicated with the inside of the gas-filled bags, and the injection valve is a gas inlet valve which is communicated with the inside of the gas-.
4. A neutron source transfer vessel according to claim 2 or claim 3, wherein: the plane of the first shell and the plane of the second shell are respectively provided with a flange, and the first shell and the second shell are fixedly connected through the flange and a screw.
5. A neutron source transfer vessel according to claim 2 or claim 3, wherein: the first shell and the second shell are made of aluminum materials.
6. A neutron source transfer vessel according to claim 4, wherein: handles are respectively arranged on the first shell and the second shell.
7. A neutron source transfer vessel according to claim 4, wherein: the second casing be located the downside of first casing, second casing downside is equipped with the base, the second casing passes through the support to be connected with the base, the downside of base is equipped with the gyro wheel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920776837.3U CN210271811U (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201920776837.3U CN210271811U (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
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| Publication Number | Publication Date |
|---|---|
| CN210271811U true CN210271811U (en) | 2020-04-07 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201920776837.3U Active CN210271811U (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110265168A (en) * | 2019-05-28 | 2019-09-20 | 王璐 | A kind of neutron source transfer vessel |
| WO2022106175A1 (en) * | 2020-11-19 | 2022-05-27 | Endress+Hauser SE+Co. KG | Radioprotective container for radiometric measuring devices |
-
2019
- 2019-05-28 CN CN201920776837.3U patent/CN210271811U/en active Active
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110265168A (en) * | 2019-05-28 | 2019-09-20 | 王璐 | A kind of neutron source transfer vessel |
| WO2022106175A1 (en) * | 2020-11-19 | 2022-05-27 | Endress+Hauser SE+Co. KG | Radioprotective container for radiometric measuring devices |
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