CN204066757U - Meet the double-deck spent fuel storage system that criticality safety requires - Google Patents
Meet the double-deck spent fuel storage system that criticality safety requires Download PDFInfo
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- CN204066757U CN204066757U CN201420375776.7U CN201420375776U CN204066757U CN 204066757 U CN204066757 U CN 204066757U CN 201420375776 U CN201420375776 U CN 201420375776U CN 204066757 U CN204066757 U CN 204066757U
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- storage
- deck
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- storage system
- fuel assembly
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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 relates to a kind of double-deck spent fuel storage system meeting criticality safety and require, this storage system comprises storage screen work (1), multiple storage sleeve pipes (3) is provided with in described storage screen work (1), arrange double-deck irradiated fuel assembly (2) in each described storage sleeve pipe (3), each described irradiated fuel assembly (2) is arranged in described storage sleeve pipe (3) by hanging basket (4).The storage system that the utility model provides, can make full use of effective storage space, improves the storage capability of irradiated fuel assembly in storage pond; And this storage system meets the criticality safety requirement of storage.
Description
Technical field
The utility model belongs to Nuclear Power Station's Exhausted Fuels storing technology field, is specifically related to a kind of double-deck spent fuel storage system meeting criticality safety and require.
Background technology
Along with China's nuclear power generating sets are progressively gone into operation, the quantity of irradiated fuel assembly is also being doubled and redoubled.The policy of China's nuclear fuel cycle carries out aftertreatment to spentnuclear fuel, and spentnuclear fuel just needs to be transported to reprocessing plant or intermediate storage facilities, to carry out spentnuclear fuel aftertreatment from now on after the short of nuclear power station storage pond.The power plant of the in-service operation of current China mainland has produced more than 4,000 root irradiated fuel assemblies, continuations significantly increases along with the increase of the installation of China's nuclear power from now on total volume by this numeral, the irradiated fuel assembly of the nuclear power generating sets about generation about 25 tons every year of a million kilowatt.Its irradiated fuel store facility of current variant type is substantially all carry out designing according to meeting nuclear power plant's storage capacity of 10 years to 20 years, and be generally 40 years the designed life of unit and even reach 60 years, when the construction the built time of China's reprocessing plant and the reprocessing rate after building up can't meet the demands, a large amount of irradiated fuel assemblies will face long-term intermediate storage, and the storage capability therefore improving irradiated fuel assembly in limited factory site is to economy and security requirement.Irradiated fuel store is stored from the early stage mode not using neutron poison to carry out criticality safety control, the use certain forms extensively adopted up till now and the neutron poison of layout carry out criticality safety control and reach the object of intensive storage, and research burnup is trusted the application of method processed in irradiated fuel store and reaches the target of more intensive storage, various countries have all dropped into a large amount of research and practices to the Curve guide impeller of irradiated fuel store.
Utility model content
For problems of the prior art, the utility model provides a kind of double-deck spent fuel storage system meeting criticality safety and require, this accumulating structure can utilize effective space, improves the object of irradiated fuel store ability in storage pond; And the Neutron Coupling effect of upper and lower two-layer irradiated fuel assembly is almost nil, meet the criticality safety requirement of storage.
For reaching above object, the technical solution adopted in the utility model is: provide a kind of double-deck spent fuel storage system meeting criticality safety and require, this storage system comprises storage screen work, multiple storage sleeve pipes is provided with in described storage screen work, arrange double-deck irradiated fuel assembly in each described storage sleeve pipe, each described irradiated fuel assembly is arranged in described storage sleeve pipe by hanging basket.
Further, be provided with between described double-deck irradiated fuel assembly active section and be more than or equal to the thick water layer of 30cm.
Further, the height of described storage sleeve pipe is the height of two hanging baskets.
Advantageous Effects of the present utility model is:
(1) adopt storage system of the present utility model, effective storage space can be utilized, improve the storage capability of Spent fuel pit;
(2) this storage system, can guarantee the safe distance that the Neutron Coupling effect of the irradiated fuel assembly that upper and lower both sides are stored is almost nil, meets the criticality safety requirement of storage;
(3) this storage system, the centre distance between multiple storage sleeve pipe can not change because arranging double-deck irradiated fuel assembly, so storage capability increases in the irradiated fuel assembly of the rebuilding irradiated fuel assembly unit area of arranging than individual layer.
Accompanying drawing explanation
Fig. 1 is the structural representation of the double-deck spent fuel storage system of the utility model;
Fig. 2 is the structural representation of individual layer spent fuel storage system in prior art.
In figure:
1-stores screen work 2-irradiated fuel assembly 3-storage sleeve pipe 4-hanging basket 5-neutron poison
Embodiment
Below in conjunction with accompanying drawing, embodiment of the present utility model is described in further detail.
As shown in Figure 1, be the double-deck spent fuel storage system that can meet criticality safety requirement that the utility model provides, this storage system is applied in ACP100 rickle Spent fuel pit.
This storage system comprises storage screen work 1, multiple storage sleeve pipe 3 is provided with in storage screen work 1, in each storage sleeve pipe 3, double-deck irradiated fuel assembly 2 is set, each irradiated fuel assembly 2 is arranged in storage sleeve pipe 3 by hanging basket 4, establishes neutron poison 5 to meet the criticality safety requirement under intensive storage spacing in hanging basket 4.Like this, in limited unit area, improve the storage capability of Spent fuel pit, solve the problem of Spent fuel pit finite capacity.
In order to the criticality safety requirement of satisfied storage, between double-deck irradiated fuel assembly 2 active section, be provided with the water layer being greater than 30cm.
In order to conserve space, the height of storage screen work 1 is the height of two hanging baskets 4, and namely the storage sleeve pipe 3 stored in screen work 1 just can hold two irradiated fuel assemblies 2.
Storage system of the present utility model, is first placed on irradiated fuel assembly 2 in hanging basket 4, is together placed in the storage sleeve pipe 3 of spent fuel storage rack 1 by hanging basket 4 together with irradiated fuel assembly 2.Wherein, store the height of the storage sleeve pipe 3 in screen work 1 and determined by criticality safety analytical calculation for the height of the hanging basket 4 loading irradiated fuel assembly.The height design of hanging basket 4 does not almost have Neutron Coupling effect by between make to place up and down two irradiated fuel assemblies, such as, be provided with between two irradiated fuel assembly active sections and be greater than the thick water layer of 30cm.Through calculating checking, time when between highly satisfied two irradiated fuel assemblies making to place up and down of hanging basket 4 without Neutron Coupling effect, the centre distance of storage sleeve pipe also meets criticality safety requirement.Thus, can not need due to upper and lower two-layer layout between adjacent storage sleeve pipe in storage system to increase spacing, namely in the design of double-deck irradiated fuel assembly and the design of individual layer irradiated fuel assembly, the centre distance between storage sleeve pipe is identical.
Whether the former design consideration irradiated fuel assembly of ACP100 rickle Spent fuel pit adopts new irradiated fuel assembly to suppose to divide into twoth district, irradiated fuel assembly is considered as fresh fuel by I district, do not consider the reactive decline of assembly because burnup causes, in the storage screen work in I district, the storage spacing of storage sleeve pipe is 28cm, adopts cadmium to make neutron poison.II district considers that the reactivity that irradiated fuel assembly causes due to irradiation reduces, and storage sleeve pipe have employed more intensive storage spacing 24cm, and employing boron steel is neutron poison.As shown in Figure 2, the design of the spent fuel storage rack of single layer of stored is shown; Be the side view of 5 × 6 screen works, vertical being placed in the storage sleeve pipe 3 of storage screen work 1 of irradiated fuel assembly 2.
Compare can find out from the structural representation of Fig. 1 and Fig. 2, the spent fuel storage system of rebuilding makes the storage capability in Spent fuel pit in unit area increase.
It should be noted that, the irradiated fuel assembly that ACP100 rickle adopts is the square irradiated fuel assembly of 17 × 17 arrangements.Fuel rod in assembly is contained in Zr alloy cladding pipe by low enrichment UO2 pellet and forms, and fills the helium with certain pressure in fuel rod.Fuel rod active section height is 215cm, fuel rod pitch 1.26cm, and containing 264 fuel rods and 24 guide pipes in irradiated fuel assembly, in current fuel management scheme, the highest initial enrichment of irradiated fuel assembly is 4.2%.Thus, spent fuel storage system specification of the present utility model can design according to the specification of irradiated fuel assembly.
The spent fuel storage system that the utility model meets criticality safety requirement is not limited to above-mentioned embodiment, and those skilled in the art draw other embodiment according to the technical solution of the utility model, belong to technological innovation scope of the present utility model equally.
Claims (3)
1. the double-deck spent fuel storage system meeting criticality safety and require, this storage system comprises storage screen work (1), it is characterized in that: in described storage screen work (1), be provided with multiple storage sleeve pipes (3), arrange double-deck irradiated fuel assembly (2) in each described storage sleeve pipe (3), each described irradiated fuel assembly (2) is arranged in described storage sleeve pipe (3) by hanging basket (4).
2. meet the double-deck spent fuel storage system that criticality safety requires as claimed in claim 1, it is characterized in that: be provided with between described double-deck irradiated fuel assembly (2) active section and be more than or equal to the thick water layer of 30cm.
3. meet the double-deck spent fuel storage system that criticality safety requires as claimed in claim 2, it is characterized in that: the height of described storage sleeve pipe (3) is the height of two hanging baskets (4).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420375776.7U CN204066757U (en) | 2014-07-08 | 2014-07-08 | Meet the double-deck spent fuel storage system that criticality safety requires |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420375776.7U CN204066757U (en) | 2014-07-08 | 2014-07-08 | Meet the double-deck spent fuel storage system that criticality safety requires |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN204066757U true CN204066757U (en) | 2014-12-31 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
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| CN201420375776.7U Expired - Fee Related CN204066757U (en) | 2014-07-08 | 2014-07-08 | Meet the double-deck spent fuel storage system that criticality safety requires |
Country Status (1)
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| CN (1) | CN204066757U (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104143362A (en) * | 2014-07-08 | 2014-11-12 | 中国核电工程有限公司 | Double-layer spent fuel storage system capable of meeting requirement on criticality safety |
| CN107949885A (en) * | 2015-09-11 | 2018-04-20 | Tn国际公司 | For storing and/or transporting the improved storage device of nuclear fuel assembly |
| CN108389633A (en) * | 2018-01-29 | 2018-08-10 | 岭东核电有限公司 | Fuel assembly fixed structure and its bogey |
-
2014
- 2014-07-08 CN CN201420375776.7U patent/CN204066757U/en not_active Expired - Fee Related
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104143362A (en) * | 2014-07-08 | 2014-11-12 | 中国核电工程有限公司 | Double-layer spent fuel storage system capable of meeting requirement on criticality safety |
| CN107949885A (en) * | 2015-09-11 | 2018-04-20 | Tn国际公司 | For storing and/or transporting the improved storage device of nuclear fuel assembly |
| CN108389633A (en) * | 2018-01-29 | 2018-08-10 | 岭东核电有限公司 | Fuel assembly fixed structure and its bogey |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20141231 Termination date: 20210708 |
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| CF01 | Termination of patent right due to non-payment of annual fee |