CN107068221B - Neutron absorption assembly for spent fuel storage grillwork - Google Patents
Neutron absorption assembly for spent fuel storage grillwork Download PDFInfo
- Publication number
- CN107068221B CN107068221B CN201710114428.2A CN201710114428A CN107068221B CN 107068221 B CN107068221 B CN 107068221B CN 201710114428 A CN201710114428 A CN 201710114428A CN 107068221 B CN107068221 B CN 107068221B
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- China
- Prior art keywords
- plate
- spent fuel
- fuel storage
- neutron
- storage
- 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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- 239000002915 spent fuel radioactive waste Substances 0.000 title claims abstract description 53
- 238000010521 absorption reaction Methods 0.000 title claims abstract description 36
- 239000011358 absorbing material Substances 0.000 claims abstract description 11
- 238000005253 cladding Methods 0.000 claims abstract description 8
- 239000000446 fuel Substances 0.000 claims description 5
- 229910052580 B4C Inorganic materials 0.000 claims description 3
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 3
- 229910052782 aluminium Inorganic materials 0.000 claims description 3
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 3
- 239000006096 absorbing agent Substances 0.000 claims description 2
- 238000009434 installation Methods 0.000 claims description 2
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 230000004075 alteration Effects 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000000750 progressive effect Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/06—Magazines for holding fuel elements or control elements
- G21C19/07—Storage racks; Storage pools
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/40—Arrangements for preventing occurrence of critical conditions, e.g. during storage
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Fuel Combustion (AREA)
- Radiation-Therapy Devices (AREA)
Abstract
The invention provides a neutron absorption assembly for a spent fuel storage grillwork, which comprises a storage cavity; a plate surrounding one end of the storage chamber; the bottom plate is arranged at the other end opposite to the coaming; the support is arranged below the bottom plate and used for supporting the spent fuel storage grillwork; and the fixed neutron absorbing material and the cladding are arranged on the periphery of the storage cavity. The spare neutron absorbing assembly for the spent fuel storage grillwork provided by the embodiment effectively improves the safety of spent fuel storage, and once the fixed neutron absorbing plate fails, the spare neutron absorbing assembly can be inserted to ensure the critical safety of spent fuel storage. Meanwhile, the standby neutron absorption assembly can be used as a key component for prolonging the service life of the spent fuel storage grillwork, and the economy of the nuclear power station is improved.
Description
Technical Field
The invention relates to spent fuel storage in a nuclear power plant, in particular to a spare neutron absorption assembly for a spent fuel storage grid.
Background
The spent fuel storage grillwork is positioned in the spent fuel storage pool of the auxiliary factory building, and mainly provides a storage space for spent fuel assemblies discharged out of the reactor core, and temporarily stores new and spent fuel assemblies (including the inserts) to be piled. The spent fuel storage grillwork should meet the requirements of cooling and subcritical storage of the fuel assembly for all expected conditions. Spent fuel discharged from a nuclear power plant reactor has strong radioactivity and continues to release heat, and needs to be stored in a spent fuel pool for a quite long time, and after the condition of export is met (typically 10 calendar years), the spent fuel is exported to a special storage facility. Because of the high cost of long-term spent fuel storage facilities and fuel export which are not mature in China, the improvement of the in-plant storage capacity of a nuclear power plant is a main countermeasure at present, namely, the dense spent fuel storage technology is adopted. On the premise of ensuring safety, the storage of the spent fuel assemblies in the nuclear power plant as much as possible is a key technical problem of the design of the spent fuel storage grillwork. The fixed neutron absorbing material is a key component of the spent fuel storage grillwork, and has the requirements and measures of in-service monitoring, but if failure occurs, the neutron absorbing material is replaced without means except that the spent fuel storage grillwork is scrapped as a whole, so that the economy is poor, and the operation is very inconvenient.
Disclosure of Invention
Aiming at the defects of the prior art, the invention provides a spare neutron absorption component for a spent fuel storage grillwork.
The neutron absorption assembly for the spent fuel storage grillwork comprises
A storage chamber;
a shroud surrounding one end of the storage chamber;
the bottom plate is arranged at the other end opposite to the coaming;
the support is arranged below the bottom plate and used for supporting the spent fuel storage grillwork; and
The fixed neutron absorbing material and the cladding are arranged on the periphery of the storage cavity.
Preferably, the neutron absorber further comprises a baffle plate, a support plate, a neutron absorption plate, a lining plate, a cover plate I and a cover plate II, wherein the baffle plate is vertically arranged on one side surface of the support plate and connected with the support plate for the installation of a standby neutron absorption assembly; the cover plate I, the cover plate II and the supporting plate are welded with each other; the neutron absorbing plate is wrapped between the cover plate I and the cover plate II.
Preferably, the neutron absorption plate is an aluminum-based boron carbide plate.
Preferably, the neutron absorbing plate covers the active area of the fuel assembly.
Preferably, the storage device further comprises a standby neutron absorbing assembly stop bar, wherein the standby neutron absorbing assembly stop bar is arranged on the storage sleeve and is positioned below the fixed neutron absorbing material and the cladding.
Compared with the prior art, the invention has the following beneficial effects:
1. the spare neutron absorption assembly for the spent fuel storage grillwork provided by the invention effectively improves the safety of spent fuel storage, and once the fixed neutron absorption plate fails, the spare neutron absorption assembly can be inserted to ensure the critical safety of spent fuel storage. Meanwhile, the standby neutron absorption assembly can be used as a key component for prolonging the service life of the spent fuel storage grillwork, and the economy of the nuclear power station is improved.
2. According to the spare neutron absorption assembly for the spent fuel storage grillwork, when the fixed neutron absorption plate of the spent fuel storage grillwork fails, the spare neutron absorption assembly can be inserted, so that the safety of spent fuel storage is improved; the spare neutron absorption assembly can be used for prolonging the service life of the spent fuel storage grillwork and improving the economy of the nuclear power station; the spare neutron absorption assembly is simple in structure, and the neutron absorption plate is coated by the stainless steel cover plate; the spare neutron absorbing assembly is convenient to install and discharge, and can be operated by using a special tool.
Drawings
FIG. 1 is a schematic illustration of a spent fuel storage rack employing a back-up neutron absorbing assembly provided by the present invention.
Fig. 2 is an enlarged view of I in fig. 1.
FIG. 3 is a schematic view of a spent fuel storage compartment according to the present invention.
FIG. 4 is a schematic view of an alternate neutron absorption assembly provided by the present invention.
Fig. 5 is a cross-sectional view of the structure shown in fig. 4.
Wherein: 1-a storage chamber; 2-coaming; 3-supporting seats; 4-a bottom plate; 5-a back-up neutron absorption assembly; 6-a storage sleeve; 7-a stationary neutron absorbing material and an enclosure; 8-a spare neutron absorbing assembly stop bar; 9-baffle plates; 10-supporting plates; 11-neutron absorbing plate; 12-lining board; 13-cover plate I; 14-cover plate II.
Detailed Description
In order that the above-recited objects, features and advantages of the present invention will become more readily apparent, a more particular description of the invention will be rendered by reference to the appended drawings and appended detailed description.
As shown in fig. 1-5, the neutron absorbing assembly for spent fuel storage grillwork comprises a storage chamber 1; a shroud 2, the shroud 2 surrounding one end of the storage chamber 1; a bottom plate 4, the bottom plate 4 being provided at the other end opposite to the shroud 2; the support 3 is arranged below the bottom plate 4 and is used for supporting the spent fuel storage grillwork; and a stationary neutron absorbing material and cladding 7, the stationary neutron absorbing material and cladding 7 being disposed at the periphery of the storage chamber 1.
The spare neutron absorption assembly of the spent fuel storage grillwork also comprises a baffle plate 9, a support plate 10, a neutron absorption plate 11, a lining plate 12, a cover plate I13 and a cover plate II 14, wherein the baffle plate 9 is vertically arranged on one side surface of the support plate 10 and connected with the support plate 10 for mounting the spare neutron absorption assembly; the cover plate I13, the cover plate II 14 and the support plate 10 are welded to each other; the neutron absorbing plate 11 is wrapped between the shroud plate I13 and the shroud plate II 14. The neutron absorption plate is an aluminum-based boron carbide plate. The neutron absorbing plate covers an active area of the fuel assembly.
The spare neutron absorbing assembly of the spent fuel storage grillwork further comprises a spare neutron absorbing assembly stop bar 8, wherein the spare neutron absorbing assembly stop bar is arranged on the storage sleeve 6 and is positioned below the fixed neutron absorbing material and the cladding.
Compared with the prior art, the embodiment has the following beneficial effects:
1. the spare neutron absorbing assembly for the spent fuel storage grillwork provided by the embodiment effectively improves the safety of spent fuel storage, and once the fixed neutron absorbing plate fails, the spare neutron absorbing assembly can be inserted to ensure the critical safety of spent fuel storage. Meanwhile, the standby neutron absorption assembly can be used as a key component for prolonging the service life of the spent fuel storage grillwork, and the economy of the nuclear power station is improved.
2. According to the spare neutron absorption assembly for the spent fuel storage grillwork, when the fixed neutron absorption plate of the spent fuel storage grillwork fails, the spare neutron absorption assembly can be inserted, so that the safety of spent fuel storage is improved; the spare neutron absorption assembly can be used for prolonging the service life of the spent fuel storage grillwork and improving the economy of the nuclear power station; the spare neutron absorption assembly is simple in structure, and the neutron absorption plate is coated by the stainless steel cover plate; the spare neutron absorbing assembly is convenient to install and discharge, and can be operated by using a special tool.
In the present specification, each embodiment is described in a progressive manner, and each embodiment is mainly described in a different point from other embodiments, and identical and similar parts between the embodiments are all enough to refer to each other. For the system disclosed in the embodiment, the description is relatively simple because of corresponding to the method disclosed in the embodiment, and the relevant points refer to the description of the method section.
Those skilled in the art may implement the described functionality using different approaches for each particular application, but such implementation is not intended to be limiting.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof.
Claims (3)
1. A neutron absorber assembly for spent fuel storage grillwork, comprising
A storage chamber;
a shroud surrounding one end of the storage chamber;
the bottom plate is arranged at the other end opposite to the coaming;
the support is arranged below the bottom plate and used for supporting the spent fuel storage grillwork; and
The fixed neutron absorbing material and the cladding are arranged on the periphery of the storage cavity;
the device also comprises a baffle plate, a support plate, a neutron absorption plate, a lining plate, a cover plate I and a cover plate I I, wherein the baffle plate is vertically arranged on one side surface of the support plate and is connected with the support plate for the installation of a standby neutron absorption assembly; the cover plate I, the cover plate I I, and the support plate are welded to each other; the neutron absorption plate is coated between the cover plate I and the cover plate II;
the storage sleeve is provided with a storage sleeve, and the storage sleeve is provided with a storage sleeve, a fixed neutron absorbing material and a cladding.
2. The neutron absorbing assembly for spent fuel storage grillwork according to claim 1, wherein the neutron absorbing plate is an aluminum-based boron carbide plate.
3. The spent fuel storage grid backup neutron absorbing assembly according to claim 1, wherein the neutron absorbing plate covers an active area of the fuel assembly.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710114428.2A CN107068221B (en) | 2017-02-28 | 2017-02-28 | Neutron absorption assembly for spent fuel storage grillwork |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710114428.2A CN107068221B (en) | 2017-02-28 | 2017-02-28 | Neutron absorption assembly for spent fuel storage grillwork |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN107068221A CN107068221A (en) | 2017-08-18 |
| CN107068221B true CN107068221B (en) | 2024-04-09 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710114428.2A Active CN107068221B (en) | 2017-02-28 | 2017-02-28 | Neutron absorption assembly for spent fuel storage grillwork |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107068221B (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113571217A (en) * | 2021-06-15 | 2021-10-29 | 上海核工程研究设计院有限公司 | Hollow water gap structure storage cavity for dense spent fuel storage and storage grillwork thereof |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5479463A (en) * | 1994-03-11 | 1995-12-26 | Roberts; Paul | Neutron absorbing apparatus |
| CN103021479A (en) * | 2012-11-27 | 2013-04-03 | 中国核电工程有限公司 | Movable nuclear material reactive inhibition system suitable for accident condition |
| JP2014163761A (en) * | 2013-02-22 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | Fuel storage rack |
| CN105469844A (en) * | 2015-12-29 | 2016-04-06 | 上海核工程研究设计院 | Neutron absorbing material assembly for replaceable fuel storage grillwork |
| CN205354668U (en) * | 2015-12-15 | 2016-06-29 | 中国核动力研究设计院 | Quick safe shutdown system of nuclear power plant |
| CN106229020A (en) * | 2016-08-26 | 2016-12-14 | 上海核工程研究设计院 | A kind of Spent Fuel Pool expansion method |
| CN106356107A (en) * | 2016-11-11 | 2017-01-25 | 上海核工程研究设计院 | Additively manufactured spent fuel storage grillage |
| CN206619406U (en) * | 2017-02-28 | 2017-11-07 | 上海核工程研究设计院 | A kind of standby neutron-absorbing component of spent fuel storage rack |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9685248B2 (en) * | 2012-06-22 | 2017-06-20 | Holtec International, Inc. | Snap-in insert for reactivity control in spent nuclear fuel pools and casks |
-
2017
- 2017-02-28 CN CN201710114428.2A patent/CN107068221B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5479463A (en) * | 1994-03-11 | 1995-12-26 | Roberts; Paul | Neutron absorbing apparatus |
| CN103021479A (en) * | 2012-11-27 | 2013-04-03 | 中国核电工程有限公司 | Movable nuclear material reactive inhibition system suitable for accident condition |
| JP2014163761A (en) * | 2013-02-22 | 2014-09-08 | Mitsubishi Heavy Ind Ltd | Fuel storage rack |
| CN205354668U (en) * | 2015-12-15 | 2016-06-29 | 中国核动力研究设计院 | Quick safe shutdown system of nuclear power plant |
| CN105469844A (en) * | 2015-12-29 | 2016-04-06 | 上海核工程研究设计院 | Neutron absorbing material assembly for replaceable fuel storage grillwork |
| CN106229020A (en) * | 2016-08-26 | 2016-12-14 | 上海核工程研究设计院 | A kind of Spent Fuel Pool expansion method |
| CN106356107A (en) * | 2016-11-11 | 2017-01-25 | 上海核工程研究设计院 | Additively manufactured spent fuel storage grillage |
| CN206619406U (en) * | 2017-02-28 | 2017-11-07 | 上海核工程研究设计院 | A kind of standby neutron-absorbing component of spent fuel storage rack |
Non-Patent Citations (1)
| Title |
|---|
| 乏燃料贮存格架自主化设计;朱自强;贺小明;毛星明;黄然;曹艳芳;;机械研究与应用(第05期);105-107 * |
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| Publication number | Publication date |
|---|---|
| CN107068221A (en) | 2017-08-18 |
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| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
Address after: 200233, 29 Rainbow Road, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE |
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