CN203026161U - Cantilever type supporting device of reactor pressure vessel - Google Patents
Cantilever type supporting device of reactor pressure vessel Download PDFInfo
- Publication number
- CN203026161U CN203026161U CN2012206863909U CN201220686390U CN203026161U CN 203026161 U CN203026161 U CN 203026161U CN 2012206863909 U CN2012206863909 U CN 2012206863909U CN 201220686390 U CN201220686390 U CN 201220686390U CN 203026161 U CN203026161 U CN 203026161U
- Authority
- CN
- China
- Prior art keywords
- pressure vessel
- reactor pressure
- backing plate
- supporting
- lower flange
- 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.)
- Expired - Lifetime
Links
Images
Classifications
-
- 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The utility model 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, reactor pressure vessel fixing also support stack inner member, reactor core parts, 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, make the section diameter of piling chamber placing response core pressure vessel increase, make reactor pressure vessel and pile the chamber size and do not mate, existing supporting structure is inapplicable, need to improve supporting, make supporting base around the heap chamber of placing response core pressure vessel, take over a 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 integral body are the annular slab structure, and it is welded and fixed by endosternum and outer web; Circumferential 3 ~ 8 bearing supports that are recessed to form groove structure downwards that evenly distribute in edge on upper flange, 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 on concrete foundation, and adjusts absolute altitude and the levelness of sustained ring by the screw jack of passing lower flange; The supporting of reactor pressure vessel is propped up pad and 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 integral body.
The internal diameter of the upper flange in described sustained ring and external diameter make upper flange partly inwardly unsettled with respect to lower flange respectively less than internal diameter and the external diameter of lower flange.
Described sustained ring circumferentially stretches out and is provided with reinforcement A and the reinforcement B that is in triangular distribution in the supporting structure of the cavity structure that forms, and is provided with heat sink A and heat sink B in this zone.
Described sustained ring is provided with grout pipe, and ventilation interface both sides, the outward extending end of each bearing support are equipped with stop block, and by after the grout pipe back-grouting, make the swing offset of the whole fulcrum arrangement of stop block restriction that is fixed in concrete foundation, and then the axial displacement of limiting pressure container.
Be equipped with in described bearing support and regulate double-screw bolt to adjust the 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 the reactor pressure vessel thermal expansion produces can be satisfied.
Remarkable result of the present invention is: a kind of reactor pressure vessel cantilever support device of the present invention, situation when being applicable to the heap chamber diameter of placing response core pressure vessel and reactor pressure vessel size and not mating, need not reactor pressure vessel is redesigned, increased supporting structure for the adaptability of piling the chamber change in size, save design cost.
Description of drawings
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, a 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 Fig. 1 ~ shown in Figure 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 integral body are the 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 endosternum 17 and outer several gussets 5 that is furnished with of outer web 18, to guarantee the intensity of sustained ring 1 integral body, the internal diameter of the upper flange 16 in sustained ring 1 and external diameter are respectively less than internal diameter and the external diameter of lower flange 15, make upper flange 16 inwardly unsettled with respect to lower flange 15 parts, circumferential 3 ~ 8 bearing supports 2 that are recessed to form groove structure downwards that evenly distribute in edge on upper flange 16, 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, be furnished with reinforcement A20 and reinforcement B22 in the supporting structure of this cavity structure, form leg-of-mutton reinforced region, and be provided with heat sink A21 and heat sink B23 in this zone, lower flange 15 in sustained ring 1 is placed on concrete foundation 6, and the screw jack by passing lower flange 15 7 is adjusted absolute altitude and the levelness of sustained rings 1, and be embedded with in advance supporting embedded board 24 in the concrete foundation 6 of screw jack 7 lower ends, to prevent screw jack 7 damage concrete foundation 6 in the supporting adjustment process, grout pipe 8 is installed on sustained ring 1, and the outward extending end of each bearing support 2 is equipped with ventilation interface 4, and on this ventilation interface 4 both sides, stop block 3 is installed, and by after grout pipe 8 back-groutings, make the swing offset of the stop block 3 whole fulcrum arrangements of restriction that are fixed in concrete foundation 6, and then the axial displacement of limiting pressure container, be equipped with in bearing support 2 and regulate double-screw bolt 13 to adjust pressure vessel 19 absolute altitudes, the supporting of reactor pressure vessel 19 is propped up pad 14 and 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 satisfy the radial displacement that the reactor pressure vessel thermal expansion produces.
In the ventilation interface 4 that distributes around sustained ring 1, ventilation interface 4 is connected with ventilating duct, cooling-air enters from a part of ventilation interface 4 around sustained ring 1, and flow out by another part ventilation interface, cooling by ventilating, can effectively reduce pressure vessel 19 outer walls and directly pass to the high temperature of concrete foundation 6 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. 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) integral body are the annular slab structure, and it is welded and fixed by endosternum (17) and outer web (18); Upper along 3 ~ 8 bearing supports (2) that are recessed to form groove structure downwards that circumferentially evenly distribute at upper flange (16), 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); Lower flange (15) in sustained ring (1) is placed on concrete foundation (6), and adjusts absolute altitude and the levelness of sustained ring (1) by the screw jack (7) of passing lower flange (15); The supporting of reactor pressure vessel (19) is propped up pad (14) by horizontal backing plate A(9) and horizontal backing plate B(10) be positioned on bearing support (2), 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), with the intensity that guarantees that sustained ring (1) is whole.
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 make upper flange (16) partly inwardly unsettled with respect to lower flange (15) respectively less than internal diameter and the external diameter of 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 and is provided with the reinforcement A(20 that is in triangular distribution in the supporting structure of the cavity structure that forms) and reinforcement B(22), and be provided with heat sink A(21 in this zone) 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 equipped with stop block (3), and by after grout pipe (8) back-grouting, make the swing offset of the whole fulcrum arrangement of stop block (3) restriction that is fixed in concrete foundation (6), 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: be equipped with in described bearing support (2) 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 equipped 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 the reactor pressure vessel thermal expansion produces can be satisfied.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012206863909U CN203026161U (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012206863909U CN203026161U (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203026161U true CN203026161U (en) | 2013-06-26 |
Family
ID=48650127
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2012206863909U Expired - Lifetime CN203026161U (en) | 2012-12-13 | 2012-12-13 | Cantilever type supporting device of reactor pressure vessel |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN203026161U (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103871497A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Cantilever type supporting device of reactor pressure vessel |
| CN106051722A (en) * | 2016-06-15 | 2016-10-26 | 中广核工程有限公司 | Lower horizontal supporting structure of nuclear power plant vapor generator |
| CN108986932A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization for multi-vessel system is layered supporting arrangement |
| CN109830314A (en) * | 2019-01-29 | 2019-05-31 | 中广核工程有限公司 | Reactor pressure vessel position limiting structure |
-
2012
- 2012-12-13 CN CN2012206863909U patent/CN203026161U/en not_active Expired - Lifetime
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103871497A (en) * | 2012-12-13 | 2014-06-18 | 中国核动力研究设计院 | Cantilever type supporting device of reactor pressure vessel |
| CN106051722A (en) * | 2016-06-15 | 2016-10-26 | 中广核工程有限公司 | Lower horizontal supporting structure of nuclear power plant vapor generator |
| CN106051722B (en) * | 2016-06-15 | 2018-05-29 | 中广核工程有限公司 | Nuclear power station steam generator lower horizontal supporting structure |
| CN108986932A (en) * | 2018-08-01 | 2018-12-11 | 中广核研究院有限公司 | Modularization for multi-vessel system is layered supporting arrangement |
| CN108986932B (en) * | 2018-08-01 | 2023-10-31 | 中广核研究院有限公司 | Modular layered support for multi-container systems |
| 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 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103871497A (en) | Cantilever type supporting device of reactor pressure vessel | |
| CN203026161U (en) | Cantilever type supporting device of reactor pressure vessel | |
| CN103474105B (en) | A kind of reactor pressure vessel modular bearing support | |
| CN103871496A (en) | Integrated reactor roof structure for pressurized water reactor | |
| CN202627547U (en) | Device for installing penetrating piece sleeving pipe of steel containment for nuclear island of nuclear power station | |
| CN109616225B (en) | In-pile component supporting base with gamma shielding and flow distribution functions | |
| CN205869842U (en) | High temperature gas cooled piles shaft mouth built -in fitting and organizes auxiliary device for butt weld | |
| CN204267229U (en) | Offshore wind turbine generator foundation structure opens ice damping device | |
| CN205984290U (en) | Pond formula structural response heap | |
| CN203026159U (en) | Integrated reactor roof structure of pressurized water reactor | |
| CN202650562U (en) | Modularized seat support for reactor pressure vessel | |
| Doshi et al. | ITER Cryostat—An overview and design progress | |
| CN103500590A (en) | Connection structure for inlet of high-temperature gas cooled reactor main helium fan | |
| CN104700906B (en) | A kind of equipment gate end socket | |
| CN203134394U (en) | Pull bar device for upper horizontal support of steam generator at nuclear power station | |
| CN103050160A (en) | Pull rod device for horizontal support at upper part of vapor generator in nuclear power station | |
| CN204928596U (en) | Adjustable magnetic ring box of photovoltaic inverter | |
| CN203308045U (en) | Adjusting device applied to nuclear island steel lining | |
| CN203322488U (en) | Guiding thermal pipe | |
| CN203026179U (en) | Novel installing device for radiation sample stand | |
| CN203839817U (en) | Power transmission line foundation finished product protection cover | |
| CN207131532U (en) | A kind of adjustable platform suspension ring and tower frame for wind generating set for Wind turbines | |
| CN205531590U (en) | Construction and installation structure of big shaped steel feed bin | |
| CN203026163U (en) | CRDM (Control Rod Drive Mechanism) cooling coaming and air duct assembly adaptive to integrated reactor roof | |
| CN104141373B (en) | A kind of adjusting apparatus being applied to nuclear island Leak-tight liner |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CX01 | Expiry of patent term |
Granted publication date: 20130626 |
|
| CX01 | Expiry of patent term |