CN205334974U - Removable formula neutron absorbing material's fuel storage screen work - Google Patents
Removable formula neutron absorbing material's fuel storage screen work Download PDFInfo
- Publication number
- CN205334974U CN205334974U CN201521126765.6U CN201521126765U CN205334974U CN 205334974 U CN205334974 U CN 205334974U CN 201521126765 U CN201521126765 U CN 201521126765U CN 205334974 U CN205334974 U CN 205334974U
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- screen work
- neutron
- die cavity
- molectron
- base plate
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- 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
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Abstract
The utility model provides a removable formula neutron absorbing material's fuel storage screen work includes: the die cavity sub -assembly, chamber type sub -assembly is equipped with two at least die cavities, the neutron absorbs the subassembly, the neutron absorbs the subassembly and plants between two adjacent die cavities, the bottom plate, the bottom plate is located the neutron absorbs the below of subassembly, with the lower extreme welding of die cavity sub -assembly, the supporting foot, the supporting foot is located the below of bottom plate, through nut and double -screw bolt and the connection can be dismantled to the bottom plate. The utility model provides a removable formula neutron absorbing material's fuel storage screen work, not only sound construction, and easily processing, the welding volume is little, and welding deformation easily controls.
Description
Technical field
This utility model relates to the bunkering screen work of a kind of changeable type neutron absorber material。
Background technology
Spent fuel storage rack provides storage space principally for the irradiated fuel assembly drawing off reactor core, need to ensure that the fuel assembly deposited can meet criticality safety requirement under various accident conditionses。
For depositing and protect the bunkering screen work body construction of fuel assembly, not only to ensure sufficient intensity, reliability, be beneficial to convection current cooling, to be also prone to processing, reduce welding deformation, also should adapt to the Spent Fuel Pool of various storage capacity and dimensional requirement simultaneously。
Current all kinds of spent fuel storage racks are in the fabrication process, it is common to have that welding capacity is big, difficulty is high, and storage chamber is easily deformed, neutron absorber material in screen work such as cannot change at the problem, it addition, some storage screen work also needs to process multiple parts, cause manufacturing process complicated。
Utility model content
This utility model is for the deficiencies in the prior art, it is proposed to the bunkering screen work of a kind of changeable type neutron absorber material。
The bunkering screen work of changeable type neutron absorber material includes:
Die cavity molectron；Described lumen type molectron is provided with at least two die cavity；
Neutron-absorbing assembly；Described neutron-absorbing assembly is inserted between adjacent two die cavity；
Base plate；Described base plate is positioned at the lower section of described neutron-absorbing assembly；Weld with the lower end of described die cavity molectron；
Support foot；Described support foot is positioned at the lower section of described base plate, is removably connected by nut and stud and described base plate。
Preferably, described die cavity molectron adopts L-type angle steel assembly welding to be spliced to form。
Preferably, compacting part is also included；Described compacting part is welded on described die cavity top, for described neutron-absorbing assembly is fixed on described die cavity molectron。
Preferably, described base plate offers discharge orifice, it is simple to convection current cools down。
Preferably, the top of described neutron-absorbing assembly is provided with triangle guide pad, and described triangle guide pad can serve as the targeting port of bunkering screen work。
Compared with prior art, this utility model has the advantages that
1, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, adopts L-type corrosion resistant plate assembly welding forming cavity molectron, and is spliced into frame structure body, not only sound construction, and is prone to processing, and welding capacity is little, and welding deformation is easy to control。
2, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, neutron absorber can be individually replaced, and reduces cost。
3, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, it is possible to adapt to various storage chamber spacing and fuel pit screen work is arranged。
Accompanying drawing explanation
Fig. 1 is the front view of the bunkering screen work of the changeable type neutron absorber material meeting this utility model preferred embodiment。
Fig. 2 is the A-A sectional view of structure shown in Fig. 1。
Fig. 3 is the partial enlarged drawing of structure shown in Fig. 1。
Fig. 4 is the schematic diagram of the die cavity molectron meeting this utility model preferred embodiment。
Detailed description of the invention
Understandable for enabling above-mentioned purpose of the present utility model, feature and advantage to become apparent from, below in conjunction with the drawings and specific embodiments, this utility model is described in further detail。
As Figure 1-4, the bunkering screen work of changeable type neutron absorber material includes:
Die cavity molectron 1；Described lumen type molectron 1 is provided with at least two die cavity 11；
Neutron-absorbing assembly 2；Described neutron-absorbing assembly 2 is inserted between adjacent two die cavity 11；
Base plate 3；Described base plate 3 is positioned at the lower section of described neutron-absorbing assembly 2；Weld with the lower end of described die cavity molectron 1；
Support foot 4；Described support foot 4 is positioned at the lower section of described base plate 3, is removably connected with described base plate 3 by nut and stud 5。
Preferably, described die cavity molectron 1 adopts L-type angle steel assembly welding to be spliced to form。
Preferably, compacting part is also included；Described compacting part is welded on described die cavity top, for described neutron-absorbing assembly is fixed on described die cavity molectron。
Preferably, described base plate offers discharge orifice, it is simple to convection current cools down。
Preferably, the top of described neutron-absorbing assembly 2 is provided with triangle guide pad 21, and described triangle guide pad 21 can serve as the targeting port of bunkering screen work。
Compared with prior art, this utility model has the advantages that
1, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, adopts L-type corrosion resistant plate assembly welding forming cavity molectron, and is spliced into frame structure body, not only sound construction, and is prone to processing, and welding capacity is little, and welding deformation is easy to control。
2, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, neutron absorber can be individually replaced, and reduces cost。
3, the bunkering screen work of the changeable type neutron absorber material that this utility model provides, it is possible to adapt to various storage chamber spacing and fuel pit screen work is arranged。
In this specification, each embodiment adopts the mode gone forward one by one to describe, and what each embodiment stressed is the difference with other embodiments, between each embodiment identical similar portion mutually referring to。For system disclosed in embodiment, owing to corresponding to the method disclosed in Example, so what describe is fairly simple, relevant part illustrates referring to method part。
Those skilled in the art specifically can should be used for using different methods to realize described function to each, but this realization is it is not considered that exceed scope of the present utility model。
Obviously, utility model can be carried out various change and modification without deviating from spirit and scope of the present utility model by those skilled in the art。So, if these amendments of the present utility model and modification belong within the scope of this utility model claim and equivalent technologies thereof, then this utility model is also intended to include these change and modification。
Claims (5)
1. the bunkering screen work of a changeable type neutron absorber material, it is characterised in that including:
Die cavity molectron；Described lumen type molectron is provided with at least two die cavity；
Neutron-absorbing assembly；Described neutron-absorbing assembly is inserted between adjacent two die cavity；
Base plate；Described base plate is positioned at the lower section of described neutron-absorbing assembly；Weld with the lower end of described die cavity molectron；
Support foot；Described support foot is positioned at the lower section of described base plate, is removably connected by nut and stud and described base plate。
2. the bunkering screen work of changeable type neutron absorber material as claimed in claim 1, it is characterised in that described die cavity molectron adopts L-type angle steel assembly welding to be spliced to form。
3. the bunkering screen work of changeable type neutron absorber material as claimed in claim 1, it is characterised in that also include compacting part；Described compacting part is welded on described die cavity top, for described neutron-absorbing assembly is fixed on described die cavity molectron。
4. the bunkering screen work of changeable type neutron absorber material as claimed in claim 1, it is characterised in that described base plate offers discharge orifice。
5. the bunkering screen work of changeable type neutron absorber material as claimed in claim 1, it is characterised in that the top of described neutron-absorbing assembly is provided with triangle guide pad。
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201521126765.6U CN205334974U (en) | 2015-12-29 | 2015-12-29 | Removable formula neutron absorbing material's fuel storage screen work |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201521126765.6U CN205334974U (en) | 2015-12-29 | 2015-12-29 | Removable formula neutron absorbing material's fuel storage screen work |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN205334974U true CN205334974U (en) | 2016-06-22 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201521126765.6U Active CN205334974U (en) | 2015-12-29 | 2015-12-29 | Removable formula neutron absorbing material's fuel storage screen work |
Country Status (1)
| Country | Link |
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| CN (1) | CN205334974U (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105405482A (en) * | 2015-12-29 | 2016-03-16 | 上海核工程研究设计院 | Fuel storage grid with replaceable neutron absorption materials |
-
2015
- 2015-12-29 CN CN201521126765.6U patent/CN205334974U/en active Active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105405482A (en) * | 2015-12-29 | 2016-03-16 | 上海核工程研究设计院 | Fuel storage grid with replaceable neutron absorption materials |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |