CN103871497A - Cantilever type supporting device of reactor pressure vessel - Google Patents
Cantilever type supporting device of reactor pressure vessel Download PDFInfo
- Publication number
- CN103871497A CN103871497A CN201210538861.6A CN201210538861A CN103871497A CN 103871497 A CN103871497 A CN 103871497A CN 201210538861 A CN201210538861 A CN 201210538861A CN 103871497 A CN103871497 A CN 103871497A
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- pressure vessel
- reactor pressure
- backing plate
- supporting
- lower flange
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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 invention relates to the technical field of a supporting of a reactor pressure vessel of a nuclear power station and particularly discloses a cantilever type supporting device of the reactor pressure vessel. An annular-plate-shaped upper flange and an annular-plate-shaped lower flange in a supporting ring in the supporting device are welded and fixed through an inner web and an outer web; 3-8 supporting supports which are concave to form groove structures are uniformly distributed along the periphery of the upper edge of the upper flange; the upper flange, the lower flange and the outer web at the corresponding parts of each supporting support extend outwards to form a supporting structure with a cavity structure; the end part of the supporting structure is provided with a ventilation connector; the lower flange in the supporting ring is placed on a concrete foundation; and the elevation and the horizontal degree of the supporting ring can be adjusted through a spiral jack which penetrates through the lower flange. The supporting device is suitable for a condition that a reactor cavity diameter of the reactor pressure vessel is not matched with the size of the reactor pressure vessel; and the reactor pressure vessel does not need to be repeatedly designed so that the adaptability of the supporting structure to the change of the size of the reactor cavity is increased and the design cost is saved.
Description
Technical field
The invention belongs to the supporting technology field of nuclear power plant reactor pressure vessel, be specifically related to a kind of reactor pressure vessel cantilever support device.
Background technology
Reactor pressure vessel is one of key equipment of whole nuclear power plant reactor and a circuit system, is the important component part of pressure boundary.In nuclear power station, the fixing also support stack inner member of reactor pressure vessel, heap core components, control rod drive mechanisms (CRD), heap roof construction etc.; In containment, for effective fixation reaction core pressure vessel, guarantee the safe operation of whole reactor, the supporting structure of reactor pressure vessel must be set.
ACP1000 is domestic three generations's nuclear power technology, owing to having increased heap chamber flood system, the section diameter of piling chamber placing response core pressure vessel is increased, reactor pressure vessel is not mated with heap chamber size, existing supporting structure is inapplicable, need to improve supporting, make supporting base around the heap chamber of placing response core pressure vessel, take over pad with reactor pressure vessel again simultaneously and be connected.
Summary of the invention
The object of the present invention is to provide a kind of reactor pressure vessel cantilever support device, can realize the supporting to reactor pressure vessel, solved heap chamber and the unmatched problem of reactor pressure vessel size of nuclear power station placing response core pressure vessel.
Technical scheme of the present invention is as follows: a kind of reactor pressure vessel cantilever support device, this fulcrum arrangement comprises sustained ring, bearing support and ventilation interface, wherein, sustained ring comprises upper flange, lower flange, endosternum and outer web, upper flange and lower flange entirety are annular slab structure, and it is welded and fixed by endosternum and outer web; On upper flange, be uniformly distributed circumferentially 3 ~ 8 bearing supports that are recessed to form groove structure downwards, and upper flange, lower flange and the outer web of each bearing support institute corresponding position all stretch out, form the supporting structure of cavity structure, and the end of this supporting structure is provided with ventilation interface; Lower flange in sustained ring is placed in concrete foundation, and adjusts absolute altitude and the levelness of sustained ring by the screw jack through lower flange; The supporting pad of reactor pressure vessel is positioned on bearing support by horizontal backing plate A and horizontal backing plate B, and can mutually slide between horizontal backing plate A and horizontal backing plate B.
Between described upper flange and lower flange, and endosternum and outer web be provided with several gussets outward, to guarantee the intensity of sustained ring entirety.
The internal diameter of the upper flange in described sustained ring and external diameter are less than respectively internal diameter and the external diameter of lower flange, make upper flange inwardly unsettled with respect to lower flange part.
Described sustained ring circumferentially stretches out in the supporting structure of formed cavity structure and is provided with the reinforcement A and the reinforcement B that are in triangular distribution, and in this region, is provided with heat sink A and heat sink B.
Described sustained ring is provided with grout pipe, and ventilation interface both sides, the outward extending end of each bearing support are provided with stop block, and by after grout pipe back-grouting, make to be fixed on the swing offset that stop block in concrete foundation limits whole fulcrum arrangement, and then the axial displacement of limiting pressure container.
In described bearing support, be provided with and regulate double-screw bolt to adjust pressure vessel absolute altitude, at horizontal backing plate A and horizontal backing plate B both sides, sidepiece backing plate A and sidepiece backing plate B are installed, and can slide between sidepiece backing plate A and sidepiece backing plate B, the adjustment to pressure vessel axis and levelness can be realized, the radial displacement that reactor pressure vessel thermal expansion produces can be met.
Remarkable result of the present invention is: a kind of reactor pressure vessel cantilever support device of the present invention, situation when the heap chamber diameter that is applicable to placing response core pressure vessel does not mate with reactor pressure vessel size, without reactor pressure vessel is redesigned, increase the adaptability of supporting structure for heap chamber change in size, saved design cost.
Accompanying drawing explanation
Fig. 1 is a kind of reactor pressure vessel cantilever support device vertical view of the present invention;
Fig. 2 is bearing support cut-open view in a kind of reactor pressure vessel cantilever support device of the present invention;
Fig. 3 is sustained ring cut-open view in a kind of reactor pressure vessel cantilever support device of the present invention;
Fig. 4 is bearing support schematic diagram in a kind of reactor pressure vessel cantilever support device of the present invention;
Fig. 5 is bearing support side view in a kind of reactor pressure vessel cantilever support device of the present invention;
Fig. 6 is the ventilation schematic diagram of a kind of reactor pressure vessel cantilever support device of the present invention;
In figure: 1, sustained ring; 2, bearing support; 3, stop block; 4, ventilation interface; 5, gusset; 6, concrete foundation; 7, screw jack; 8, grout pipe; 9, horizontal backing plate A; 10, horizontal backing plate B; 11, sidepiece backing plate A; 12, sidepiece backing plate B; 13, regulate double-screw bolt; 14, supporting pad; 15, lower flange; 16, upper flange; 17, endosternum; 18, outer web; 19, reactor pressure vessel; 20, reinforcement A, 21, heat sink A; 22, reinforcement B; 23, heat sink B; 24, supporting embedded board.
Embodiment
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
As shown in Fig. 1 ~ Fig. 6, a kind of reactor pressure vessel cantilever support device, comprise sustained ring 1, bearing support 2 and ventilation interface 4, wherein, sustained ring 1 comprises upper flange 16, lower flange 15, endosternum 17 and outer web 18, upper flange 16 and lower flange 15 entirety are annular slab structure, it is welded and fixed by endosternum 17 and outer web 18, and between upper flange 16 and lower flange 15, and be furnished with several gussets 5 outside endosternum 17 and outer web 18, to guarantee the intensity of sustained ring 1 entirety, the internal diameter of the upper flange 16 in sustained ring 1 and external diameter are less than respectively internal diameter and the external diameter of lower flange 15, make upper flange 16 inwardly unsettled with respect to lower flange 15 parts, on upper flange 16, be uniformly distributed circumferentially 3 ~ 8 bearing supports 2 that are recessed to form groove structure downwards, for example, 3 or 6 or 8 bearing supports 2 distribute on upper flange 16, and the upper flange 16 at each bearing support 2 corresponding places, lower flange 15 and outer web 18 all stretch out, form the supporting structure of cavity structure, in the supporting structure of this cavity structure, be furnished with reinforcement A20 and reinforcement B22, form leg-of-mutton reinforced region, and in this region, be provided with heat sink A21 and heat sink B23, lower flange 15 in sustained ring 1 is placed in concrete foundation 6, and adjust absolute altitude and the levelness of sustained ring 1 by the screw jack 7 through lower flange 15, and in the concrete foundation 6 of screw jack 7 lower ends, be embedded with in advance supporting embedded board 24, to prevent that screw jack 7 from damaging concrete foundation 6 in supporting in adjustment process, grout pipe 8 is installed on sustained ring 1, and the outward extending end of each bearing support 2 is provided with ventilation interface 4, and on these ventilation interface 4 both sides, stop block 3 is installed, and by after grout pipe 8 back-groutings, make to be fixed on the swing offset that stop block 3 in concrete foundation 6 limits whole fulcrum arrangement, and then the axial displacement of limiting pressure container, in bearing support 2, be provided with and regulate double-screw bolt 13 to adjust pressure vessel 19 absolute altitudes, the supporting pad 14 of reactor pressure vessel 19 is positioned on the bearing support 2 of groove structure by horizontal backing plate A9 and horizontal backing plate B10, and can mutually slide between horizontal backing plate A9 and horizontal backing plate B10, at horizontal backing plate A9 and horizontal backing plate B10 both sides, sidepiece backing plate A11 and sidepiece backing plate B12 are installed, and can slide between sidepiece backing plate A11 and sidepiece backing plate B12, can realize the adjustment to pressure vessel 19 axis and levelness, can meet the radial displacement that reactor pressure vessel thermal expansion produces.
In the ventilation interface 4 distributing around sustained ring 1, ventilation interface 4 is connected with ventilating duct, cooling-air enters from sustained ring 1 a part of ventilation interface 4 around, and flow out by another part ventilation interface, cooling by ventilating, can effectively reduce pressure vessel 19 outer walls directly pass to concrete foundation 6 high temperature by whole fulcrum arrangement, guarantee that whole fulcrum arrangement place concrete foundation 6 is injury-free, further guarantee the safety of whole reactor supporting.
Claims (6)
1. a reactor pressure vessel cantilever support device, it is characterized in that: this fulcrum arrangement comprises sustained ring (1), bearing support (2) and ventilation interface (4), wherein, sustained ring (1) comprises upper flange (16), lower flange (15), endosternum (17) and outer web (18), upper flange (16) and lower flange (15) entirety are annular slab structure, and it is welded and fixed by endosternum (17) and outer web (18); On upper flange (16), be uniformly distributed circumferentially 3 ~ 8 bearing supports (2) that are recessed to form groove structure downwards, and the upper flange (16) of each bearing support (2) institute corresponding position, lower flange (15) and outer web (18) all stretch out, form the supporting structure of cavity structure, and the end of this supporting structure is provided with ventilation interface (4); It is upper that lower flange (15) in sustained ring (1) is placed on concrete foundation (6), and adjust absolute altitude and the levelness of sustained ring (1) by the screw jack (7) through lower flange (15); The supporting pad (14) of reactor pressure vessel (19) is by horizontal backing plate A(9) and horizontal backing plate B(10) to be positioned over bearing support (2) upper, and horizontal backing plate A(9) and horizontal backing plate B(10) between can mutually slide.
2. a kind of reactor pressure vessel cantilever support device according to claim 1, it is characterized in that: between described upper flange (16) and lower flange (15), and endosternum (17) and outer several gussets (5) that are provided with of outer web (18), to guarantee the intensity of sustained ring (1) entirety.
3. a kind of reactor pressure vessel cantilever support device according to claim 1 and 2, it is characterized in that: the internal diameter of the upper flange (16) in described sustained ring (1) and external diameter are less than respectively internal diameter and the external diameter of lower flange (15), make upper flange (16) partly inwardly unsettled with respect to lower flange (15).
4. a kind of reactor pressure vessel cantilever support device according to claim 1, it is characterized in that: described sustained ring (1) circumferentially stretches out in the supporting structure of formed cavity structure and is provided with the reinforcement A(20 being in triangular distribution) and reinforcement B(22), and in this region, be provided with heat sink A(21) and heat sink B(23).
5. a kind of reactor pressure vessel cantilever support device according to claim 1, it is characterized in that: described sustained ring (1) is provided with grout pipe (8), and each bearing support (2) outward extending end ventilation interface (4) both sides are provided with stop block (3), and by after grout pipe (8) back-grouting, make to be fixed on the swing offset that stop block (3) in concrete foundation (6) limits whole fulcrum arrangement, and then the axial displacement of limiting pressure container.
6. a kind of reactor pressure vessel cantilever support device according to claim 1, it is characterized in that: in described bearing support (2), be provided with and regulate double-screw bolt (13) to adjust pressure vessel (19) absolute altitude, at horizontal backing plate A(9) and horizontal backing plate B(10) both sides are provided with sidepiece backing plate A(11) and sidepiece backing plate B(12), and sidepiece backing plate A(11) and sidepiece backing plate B(12) between can slide, the adjustment to pressure vessel (19) axis and levelness can be realized, the radial displacement that reactor pressure vessel thermal expansion produces can be met.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538861.6A CN103871497A (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538861.6A CN103871497A (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
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| CN103871497A true CN103871497A (en) | 2014-06-18 |
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| CN201210538861.6A Pending CN103871497A (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
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Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104472724A (en) * | 2014-12-21 | 2015-04-01 | 重庆市合川区麒麟畜产品有限责任公司 | Anti-clogging beancurd sheet pouring nozzle |
| CN106297912A (en) * | 2016-10-11 | 2017-01-04 | 中国核动力研究设计院 | A kind of skirt-type supporting arrangement of reactor pressure vessel band built-in fitting |
| CN106384608A (en) * | 2016-10-11 | 2017-02-08 | 中国核动力研究设计院 | Hoop straining beam type supporting device used for reactor pressure vessel |
| CN108335762A (en) * | 2018-03-30 | 2018-07-27 | 中广核研究院有限公司 | Reactor pressure vessel and supporting structure applied to reactor pressure vessel |
| CN108986933A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization supporting arrangement for multi-vessel system |
| CN109166635A (en) * | 2018-08-01 | 2019-01-08 | 中广核研究院有限公司 | The whole supporting arrangement of integration for multi-vessel system |
| CN109243629A (en) * | 2018-08-01 | 2019-01-18 | 中广核研究院有限公司 | For reactor vessel and the modularization layered combination supporting arrangement of flexible elongate tubular |
| CN109830314A (en) * | 2019-01-29 | 2019-05-31 | 中广核工程有限公司 | Reactor pressure vessel position limiting structure |
| CN113035381A (en) * | 2021-02-03 | 2021-06-25 | 中广核工程有限公司 | Support structure of nuclear power station voltage stabilizer |
| CN114360754A (en) * | 2021-12-07 | 2022-04-15 | 华能核能技术研究院有限公司 | Method for measuring friction force of pressure container supporting and adjusting base plate |
| CN114446498A (en) * | 2020-11-04 | 2022-05-06 | 中国核工业二三建设有限公司 | Centering device for nuclear power station reactor pressure vessel in-place |
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Cited By (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104472724A (en) * | 2014-12-21 | 2015-04-01 | 重庆市合川区麒麟畜产品有限责任公司 | Anti-clogging beancurd sheet pouring nozzle |
| CN106297912A (en) * | 2016-10-11 | 2017-01-04 | 中国核动力研究设计院 | A kind of skirt-type supporting arrangement of reactor pressure vessel band built-in fitting |
| CN106384608A (en) * | 2016-10-11 | 2017-02-08 | 中国核动力研究设计院 | Hoop straining beam type supporting device used for reactor pressure vessel |
| CN106384608B (en) * | 2016-10-11 | 2018-05-08 | 中国核动力研究设计院 | A kind of reactor pressure vessel anchor ear straining beam type supporting arrangement |
| CN108335762A (en) * | 2018-03-30 | 2018-07-27 | 中广核研究院有限公司 | Reactor pressure vessel and supporting structure applied to reactor pressure vessel |
| CN108335762B (en) * | 2018-03-30 | 2024-05-10 | 中广核研究院有限公司 | Reactor pressure vessel and support structure applied to same |
| CN108986933B (en) * | 2018-08-01 | 2023-12-22 | 中广核研究院有限公司 | Modular support device for multi-container systems |
| CN108986933A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization supporting arrangement for multi-vessel system |
| CN109166635A (en) * | 2018-08-01 | 2019-01-08 | 中广核研究院有限公司 | The whole supporting arrangement of integration for multi-vessel system |
| CN109243629A (en) * | 2018-08-01 | 2019-01-18 | 中广核研究院有限公司 | For reactor vessel and the modularization layered combination supporting arrangement of flexible elongate tubular |
| CN109166635B (en) * | 2018-08-01 | 2024-05-10 | 中广核研究院有限公司 | Integrated integral support device for multi-container system |
| CN109243629B (en) * | 2018-08-01 | 2024-03-22 | 中广核研究院有限公司 | Modular layered combination support for reactor vessels and flexible long tubes |
| CN109830314A (en) * | 2019-01-29 | 2019-05-31 | 中广核工程有限公司 | Reactor pressure vessel position limiting structure |
| CN109830314B (en) * | 2019-01-29 | 2023-09-08 | 中广核工程有限公司 | Reactor pressure vessel limit structure |
| CN114446498A (en) * | 2020-11-04 | 2022-05-06 | 中国核工业二三建设有限公司 | Centering device for nuclear power station reactor pressure vessel in-place |
| CN113035381A (en) * | 2021-02-03 | 2021-06-25 | 中广核工程有限公司 | Support structure of nuclear power station voltage stabilizer |
| CN114360754A (en) * | 2021-12-07 | 2022-04-15 | 华能核能技术研究院有限公司 | Method for measuring friction force of pressure container supporting and adjusting base plate |
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Application publication date: 20140618 |