CN110265168B - Neutron source transfer container - Google Patents
Neutron source transfer container Download PDFInfo
- Publication number
- CN110265168B CN110265168B CN201910448922.1A CN201910448922A CN110265168B CN 110265168 B CN110265168 B CN 110265168B CN 201910448922 A CN201910448922 A CN 201910448922A CN 110265168 B CN110265168 B CN 110265168B
- Authority
- CN
- China
- Prior art keywords
- shell
- casing
- neutron
- neutron source
- source transfer
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Links
- 238000012546 transfer Methods 0.000 title claims abstract description 20
- 239000000463 material Substances 0.000 claims abstract description 30
- 238000002347 injection Methods 0.000 claims abstract description 10
- 239000007924 injection Substances 0.000 claims abstract description 10
- 230000005540 biological transmission Effects 0.000 claims abstract description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 17
- 229910052739 hydrogen Inorganic materials 0.000 claims description 9
- 239000001257 hydrogen Substances 0.000 claims description 9
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 3
- 229910052782 aluminium Inorganic materials 0.000 claims description 3
- 230000006978 adaptation Effects 0.000 claims description 2
- 125000004435 hydrogen atom Chemical class [H]* 0.000 claims 1
- 150000002431 hydrogen Chemical class 0.000 description 7
- 239000012188 paraffin wax Substances 0.000 description 3
- 229910000975 Carbon steel Inorganic materials 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 2
- 239000010962 carbon steel Substances 0.000 description 2
- 238000005259 measurement Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 239000004698 Polyethylene Substances 0.000 description 1
- 230000002238 attenuated effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000003814 drug Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- -1 polyethylene Polymers 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 239000000243 solution Substances 0.000 description 1
- 230000002269 spontaneous effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/023—Liquids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/015—Transportable or portable shielded containers for storing radioactive sources, e.g. source carriers for irradiation units; Radioisotope containers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/06—Details of, or accessories to, the containers
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Radiation-Therapy Devices (AREA)
- Particle Accelerators (AREA)
Abstract
The invention provides a neutron source transfer container which comprises a hemispherical first shell and a hemispherical second shell, wherein two planes of the first shell and the second shell can be mutually buckled and fixedly connected, a protruding part is arranged in the center of the plane of the first shell, a groove matched with the protruding part is formed in the second shell, a neutron source placing groove is formed in the protruding part, the first shell and the second shell are of hollow structures, neutron shielding materials are filled in the first shell and the second shell, release valves for releasing the neutron shielding materials are arranged on the first shell and the second shell, injection valves for injecting the neutron shielding materials are arranged on the first shell and the second shell, and the first shell and the second shell are made of materials convenient for neutron transmission.
Description
Technical Field
The invention relates to the technical field of radioactive substance transfer, in particular to a neutron source transfer container.
Background
The neutron source is a neutron obtained by the reaction of alpha particles emitted by the decay of a radionuclide with a (alpha, n) nucleus generated by the rich neutron, or the spontaneous fission of the radionuclide. The neutron source has the advantages of long service life, stable neutron emission, moderate volume and the like, and is widely applied to various fields of industry, agriculture, medicine and scientific research. Particularly, the neutron source for starting the nuclear reactor has irreplaceable advantages, and along with the continuous construction of the nuclear power station, the demand for the neutron source is increasing.
The external radiation protection of neutrons mainly shields fast neutrons, and the interaction of fast neutrons and substances mainly comprises elastic scattering and inelastic scattering, so that substances with more hydrogen, such as water, paraffin, polyethylene and the like, are selected as the shielding materials of neutrons. The frame structure of the storage and transportation container of the neutron source is made of carbon steel and paraffin lining, the protection material is paraffin, the carbon steel plays a role in fixation, and the problems of large mass and inconvenient transfer exist.
In addition, the neutron source is required to measure accurate neutron emissivity before use, and the neutron source is required 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 the operator is endangered.
Disclosure of Invention
In view of the problems identified in the background art, the present invention provides a neutron source transfer container that is convenient to move and to measure neutron emissivity.
The technical scheme of the invention is realized as follows:
The utility model provides a neutron source shifts container, includes hemispherical first casing and hemispherical second casing, and two planes of first casing and second casing can mutual lock fixed connection, and 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 neutron source standing groove, first casing and second casing are inside hollow structure, first casing and second casing intussuseption are filled with neutron shielding material, all are equipped with the release valve that releases neutron shielding material on first casing and the second casing, all are equipped with the injection valve that injects 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 invention is further arranged that 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.
The invention is further arranged 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, the first shell and the second shell are respectively provided with an inflatable bag, the inflatable bag is filled with hydrogen, the release valve is a release valve, the release valve is communicated with the inside of the inflatable bag, the injection valve is an air inlet valve, and the air inlet valve is communicated with the inside of the inflatable bag.
The invention is further arranged that the planes of the first shell and the second shell are respectively provided with a flange, and the first shell and the second shell are fixedly connected through the flanges and the screws.
The invention is further arranged that the first shell and the second shell are made of aluminum materials.
The invention is further arranged that handles are respectively arranged on the first shell and the second shell.
The invention is further arranged that the second shell is positioned at the lower side of the first shell, the lower side of the second shell is provided with a base, the second shell is connected with the base through a bracket, and the lower side of the base is provided with a roller.
The invention has the beneficial effects that:
The neutron source transfer container provided by the invention is provided with the hollow shell inside to bear a neutron source, and the shell is filled with the neutron shielding material, the neutron shielding material is water or hydrogen, so that the whole transfer container is lighter and convenient to move, the neutron shielding material in the shell can be conveniently injected and released, and the shell releases the neutron shielding material in the shell to make the whole container lighter under certain conditions.
Drawings
In order to more clearly illustrate the embodiments of the invention or the technical solutions of the prior art, the drawings which are used 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 invention, and that other drawings can be obtained according to these drawings without inventive faculty for a person skilled in the art.
FIG. 1 is a schematic diagram of the structure of the present invention;
Fig. 2 is a schematic structural view of the present invention.
Detailed Description
The following description of the embodiments of the present invention will be made clearly and completely with reference to the accompanying drawings, in which it is apparent that the embodiments described are only some embodiments of the present invention, but not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
The invention is illustrated below with reference to fig. 1-2:
embodiment one: 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 protruding part 30, the second shell 20 is provided with a groove 40 matched with the protruding part 30, and the protruding part 30 is provided with a neutron source placing groove 50.
The first shell 10 and the second shell 20 are hollow structures, neutron shielding materials are filled in the first shell 10 and the second shell 20, release valves 60 for releasing the neutron shielding materials are arranged on the first shell 10 and the second shell 20, injection valves 70 for injecting the neutron shielding materials are arranged on the first shell 10 and the second shell 20, and the first shell 10 and the second shell 20 are made of materials convenient for neutron transmission.
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 being filled with water, the neutron source is wrapped by a thick water layer, and emitted neutrons can be 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: embodiment 2 is basically the same as embodiment 1, except that the neutron shielding material is different, so that some structural changes are brought, a plurality of through holes communicated with the inside of 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 release valve, the release 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 discharge 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 second shell 20, and after the inflatable bag is filled with hydrogen, a neutron source positioned in the middle of the shells is completely covered by one layer of hydrogen, so that the neutron emitting shielding effect is achieved.
The flange 90 is respectively arranged on the planes of the first shell 10 and the second shell 20, the first shell 10 and the second shell 20 are fixedly connected through the flange 90 and the screws, and the connecting structure is simple and convenient to operate.
The first casing 10 and the second casing 20 are made of aluminum materials, so that neutrons can be transmitted conveniently.
Handles 32 are respectively arranged on the first shell 10 and the second shell 20, so that the manual transfer is convenient when the volume of the container is smaller.
The second shell 20 is located at the lower side of the first shell 10, the lower side of the second shell 20 is provided with a base 12, the second shell 20 is connected with the base 12 through a bracket 13, and the lower side of the base 12 is provided with a roller 14. In the technical scheme, when the volume of the container is larger, the container is convenient to move as easily as the trolley.
The invention has the beneficial effects that:
The neutron source transfer container provided by the invention is provided with the hollow shell inside to bear a neutron source, and the shell is filled with the neutron shielding material, the neutron shielding material is water or hydrogen, so that the whole transfer container is lighter and convenient to move, the neutron shielding material in the shell can be conveniently injected and released, and the shell releases the neutron shielding material in the shell to make the whole container lighter under certain conditions.
The foregoing description of the preferred embodiments of the invention is not intended to be limiting, but rather to enable any modification, equivalent replacement, improvement or the like to be made within the spirit and principles of the invention.
Claims (7)
1. A neutron source transfer container, characterized in that: including hemispherical first casing and hemispherical second casing, two planes of first casing and second casing can lock fixed connection each other, and 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 neutron source standing groove, first casing and second casing are inside hollow structure, first casing and second casing intussuseption are filled with neutron shielding material, all are equipped with the release valve that releases neutron shielding material on first casing and the second casing, all are equipped with the injection valve that injects 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.
2. The neutron source transfer container of 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. The neutron source transfer container of claim 1, wherein: the first shell and the second shell are respectively provided with a plurality of through holes communicated with the inside of the first shell and the second shell, the first shell and the second shell are respectively provided with an inflatable bag, the inflatable bag is filled with hydrogen, the release valve is a release valve, the release valve is communicated with the inside of the inflatable bag, the injection valve is an air inlet valve, and the air inlet valve is communicated with the inside of the inflatable bag.
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 flanges and the screws.
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. The neutron source transfer container of claim 4, wherein: handles are respectively arranged on the first shell and the second shell.
7. The neutron source transfer container of claim 4, wherein: the second casing be located the downside of first casing, the 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 |
|---|---|---|---|
| CN201910448922.1A CN110265168B (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910448922.1A CN110265168B (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110265168A CN110265168A (en) | 2019-09-20 |
| CN110265168B true CN110265168B (en) | 2024-08-27 |
Family
ID=67915541
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910448922.1A Active CN110265168B (en) | 2019-05-28 | 2019-05-28 | Neutron source transfer container |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110265168B (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN210271811U (en) * | 2019-05-28 | 2020-04-07 | 广东太微加速器有限公司 | Neutron source transfer container |
Family Cites Families (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES401582A1 (en) * | 1971-06-11 | 1977-07-01 | Gen Electric | A transportation container for radioactive material. (Machine-translation by Google Translate, not legally binding) |
| CA1039416A (en) * | 1974-09-19 | 1978-09-26 | Norman L. Greer | Shipping container for nuclear fuels |
| DD135657A1 (en) * | 1978-02-20 | 1979-05-16 | Guenter Vormum | PORTABLE IRRADIATOR WITH NEUTRON SOURCE |
| DE3534760C1 (en) * | 1985-09-28 | 1987-05-07 | Bbc Reaktor Gmbh | Device for generating thermal neutrons |
| DE4032343A1 (en) * | 1990-10-09 | 1992-04-16 | Apparate Und Anlagenbau German | Spent fuel transport and storage containers - with exterior angle profiles forming cavities for neutron shielding material |
| US6587536B1 (en) * | 2002-03-18 | 2003-07-01 | Holtec International, Inc. | Method and apparatus for maximizing radiation shielding during cask transfer procedures |
| CN201163545Y (en) * | 2008-02-28 | 2008-12-10 | 核电秦山联营有限公司 | Shielding device used for once neutron source component suspension |
| JP2013036859A (en) * | 2011-08-08 | 2013-02-21 | Toshiba Corp | Neutron shielding material, manufacturing method therefor, storage rack for spent nuclear fuel, and transport cask |
| CN202305438U (en) * | 2011-09-06 | 2012-07-04 | 长春工业大学 | Double-neutron-source coal on-line analyzer |
| CN104916341B (en) * | 2015-06-15 | 2017-07-14 | 中国原子能科学研究院 | A kind of radioactive source storage, pneumatic conveying and transfer device |
| CN204946553U (en) * | 2015-09-07 | 2016-01-06 | 中广核工程有限公司 | For loading and transporting the transfer container of spentnuclear fuel |
| CN205122209U (en) * | 2015-11-16 | 2016-03-30 | 中国原子能科学研究院 | Neutron source shifts container |
| CN106024085A (en) * | 2016-06-14 | 2016-10-12 | 中广核工程有限公司 | Transfer container for dry storage of nuclear power plant spent fuel |
| CN109273125A (en) * | 2018-11-21 | 2019-01-25 | 中科瑞华（安徽）中子能源技术有限公司 | A kind of multifunctional light shielding construction of radiological unit |
-
2019
- 2019-05-28 CN CN201910448922.1A patent/CN110265168B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN210271811U (en) * | 2019-05-28 | 2020-04-07 | 广东太微加速器有限公司 | Neutron source transfer container |
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| Publication number | Publication date |
|---|---|
| CN110265168A (en) | 2019-09-20 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| TA01 | Transfer of patent application right |
Effective date of registration: 20200122 Address after: 523808 room 310, building 1, No. 8, South Industrial Road, Songshanhu Park, Dongguan City, Guangdong Province Applicant after: Guangdong Taiwei accelerator Co.,Ltd. Address before: 101100 Beijing Tongzhou Canal Core Area IV-07 Block Greenbelt Building, Building 1, 22 Floors Applicant before: Wang Lu |
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| TA01 | Transfer of patent application right | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |