CN108953855B - Layered support device for reactor - Google Patents
Layered support device for reactor Download PDFInfo
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- CN108953855B CN108953855B CN201810866817.5A CN201810866817A CN108953855B CN 108953855 B CN108953855 B CN 108953855B CN 201810866817 A CN201810866817 A CN 201810866817A CN 108953855 B CN108953855 B CN 108953855B
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 44
- 238000006073 displacement reaction Methods 0.000 claims abstract description 16
- 230000002401 inhibitory effect Effects 0.000 claims abstract description 3
- 230000000670 limiting effect Effects 0.000 claims abstract description 3
- 230000007246 mechanism Effects 0.000 claims description 33
- 238000005192 partition Methods 0.000 claims description 16
- 230000000712 assembly Effects 0.000 claims description 15
- 238000000429 assembly Methods 0.000 claims description 15
- 230000003014 reinforcing effect Effects 0.000 claims description 14
- 238000000926 separation method Methods 0.000 claims description 11
- 230000008878 coupling Effects 0.000 claims description 8
- 238000010168 coupling process Methods 0.000 claims description 8
- 238000005859 coupling reaction Methods 0.000 claims description 8
- 230000002265 prevention Effects 0.000 claims description 8
- 239000003351 stiffener Substances 0.000 claims description 8
- 230000000754 repressing effect Effects 0.000 claims description 5
- 238000003825 pressing Methods 0.000 claims description 4
- 125000006850 spacer group Chemical group 0.000 claims 1
- 230000003068 static effect Effects 0.000 abstract description 3
- 230000002829 reductive effect Effects 0.000 description 9
- 230000001629 suppression Effects 0.000 description 8
- 230000000737 periodic effect Effects 0.000 description 5
- 238000003466 welding Methods 0.000 description 5
- 238000005452 bending Methods 0.000 description 4
- 230000000149 penetrating effect Effects 0.000 description 3
- 229910000831 Steel Inorganic materials 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 230000013011 mating Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 238000000638 solvent extraction Methods 0.000 description 1
Classifications
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16M—FRAMES, CASINGS OR BEDS OF ENGINES, MACHINES OR APPARATUS, NOT SPECIFIC TO ENGINES, MACHINES OR APPARATUS PROVIDED FOR ELSEWHERE; STANDS; SUPPORTS
- F16M5/00—Engine beds, i.e. means for supporting engines or machines on foundations
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16M—FRAMES, CASINGS OR BEDS OF ENGINES, MACHINES OR APPARATUS, NOT SPECIFIC TO ENGINES, MACHINES OR APPARATUS PROVIDED FOR ELSEWHERE; STANDS; SUPPORTS
- F16M7/00—Details of attaching or adjusting engine beds, frames, or supporting-legs on foundation or base; Attaching non-moving engine parts, e.g. cylinder blocks
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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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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- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention discloses a layered support device of a reactor, which comprises a support foundation, a first sliding seat component, a second sliding seat component and a horizontal support component, wherein the support foundation is arranged in a repression water tank and supported below reactor equipment, the first sliding seat component and the second sliding seat component are used for releasing thermal displacement when the reactor equipment changes cold and hot, and the horizontal support component is used for limiting the horizontal displacement of the upper part of the reactor equipment; the first sliding seat component and the second sliding seat component are arranged on the supporting base and are connected with the outer side surface of the lower part of the reactor equipment; one end of the horizontal supporting component is rotatably connected to the outer side surface of the upper part of the reactor equipment, and the other end of the horizontal supporting component is fixedly connected to the inner wall surface of the pressure-inhibiting water tank. In the invention, the reactor-loop equipment is installed and supported by a supporting foundation, and static load generated by the equipment and accessories thereof is transferred to the bottom of a reactor cabin; releasing thermal displacement of the device by the carriage assembly; the horizontal support assembly keeps the equipment in a stable state, and limits the horizontal displacement of the upper part of the equipment, so that the safety and the reliability of the reactor-loop equipment in a marine load environment are improved.
Description
Technical Field
The invention relates to the technical field of reactors, in particular to a layered supporting device for a reactor.
Background
Currently, energy supply is increasingly tense, and small stacks are touted by countries around the world, especially offshore small stacks, due to their wide applicability, shorter construction period and lower construction cost.
The offshore small-sized stacks are usually installed in a cabin, and under the marine working condition, nuclear reactor primary loop equipment is easy to receive impact loads such as sea wave impact, external impact and the like, and fatigue failure can be caused by long-term ocean periodic alternating loads in the service life. Therefore, the existing onshore reactor arrangement is not suitable for the offshore working condition, and a supporting device is necessary to be designed to realize the arrangement of the reactor equipment in the offshore working condition.
Disclosure of Invention
The technical problem to be solved by the invention is to provide a reactor layered supporting device for improving the safety and reliability of reactor equipment in a marine load environment.
The technical scheme adopted for solving the technical problems is as follows: providing a reactor layered support device, comprising a support foundation arranged in a repression water tank of a reactor cabin and supported below reactor equipment, a first sliding seat assembly and a second sliding seat assembly for releasing thermal displacement when the reactor equipment changes cold and hot, and a horizontal support assembly for limiting horizontal displacement of the upper part of the reactor equipment;
The first sliding seat assembly and the second sliding seat assembly are arranged on the supporting base and are connected with the outer side surface of the lower part of the reactor equipment; one end of the horizontal supporting component is rotatably connected to the outer side surface of the upper part of the reactor equipment, and the other end of the horizontal supporting component is fixedly connected to the inner wall surface of the repressing water tank.
Preferably, the supporting foundation comprises a supporting cylinder assembly fixed on the bottom surface of the repressurization water tank, a supporting panel arranged on the top of the supporting cylinder assembly in parallel with the bottom surface of the repressurization water tank, a first anti-sloshing separation assembly arranged on two opposite sides of the supporting cylinder assembly and connected between the supporting panel and the bottom surface of the repressurization water tank, and a transverse supporting assembly connected between the supporting cylinder assembly and the inner wall surface of the repressurization water tank;
The first and second carriage assemblies are disposed on the support panel.
Preferably, the support cylinder assembly comprises a first support cylinder for supporting a pressure vessel of the reactor apparatus, two second support cylinders for supporting a steam generator of the reactor apparatus, the two second support cylinders being oppositely disposed on opposite sides of the first support cylinder;
the first anti-sloshing separation assembly is disposed on the other opposite sides of the first support cylinder.
Preferably, the first anti-sloshing separating assembly includes at least two first anti-sloshing partitions, at least one of which is provided on each of opposite sides of the first supporting cylinder.
Preferably, the first shaking prevention baffle is provided with a first water through hole.
Preferably, the reactor layered support apparatus further comprises a second anti-sloshing separation assembly; the second anti-sloshing separation assembly is connected between the first support cylinder and the second support cylinder.
Preferably, the second anti-sloshing separating assembly includes at least two second anti-sloshing partitions; each second supporting cylinder is connected with at least one second anti-shake baffle plate with the first supporting cylinder.
Preferably, the second anti-shaking partition plate is provided with a second water through hole.
Preferably, the support cylinder assembly further comprises a stiffener assembly disposed on the outer side of the first support cylinder and/or the second support cylinder.
Preferably, the support cylinder assembly further comprises at least one coupling web; the connecting rib plate is connected between the first supporting cylinder and the reinforcing rib component on the second supporting cylinder.
Preferably, the reactor layered support apparatus further comprises a plurality of longitudinal support columns;
The plurality of longitudinal supporting columns are arranged outside the supporting cylinder assembly and/or the first anti-shaking separation assembly and are vertically connected between the supporting panel and the bottom surface of the pressure-restraining water tank.
The first sliding seat assembly comprises a first sliding seat mechanism fixed on the supporting base and a first sliding piece arranged on the first sliding seat mechanism, one end of the first sliding piece is connected to the outer side face of the reactor equipment, and the first sliding seat assembly can move back and forth in the radial direction of the reactor equipment relative to the first sliding seat mechanism;
The second sliding seat assembly comprises a second sliding seat mechanism fixed on the supporting base and a second sliding piece arranged on the second sliding seat mechanism, one end of the second sliding piece is connected to the outer side face of the reactor equipment, and the second sliding seat assembly can move back and forth in the connecting line direction between the parallel reactor equipment relative to the second sliding seat mechanism.
Preferably, the reactor layered support apparatus further comprises a slide platform disposed on a top surface of the support base; the first and second carriage mechanisms are fixed to the carriage platform.
Preferably, the first sliding seat mechanism comprises a first base and a cover plate, wherein a first sliding groove is formed in the first base, the first sliding groove penetrates through two opposite sides of the first base, and the first sliding piece is accommodated in the first sliding groove and can move back and forth in the directions of two opposite sides of the first base; the cover plate is connected to the first base and seals the top opening of the first sliding groove.
Preferably, the second sliding seat mechanism comprises a second base and a pressing plate, the second base is provided with a second sliding groove, and the second sliding piece is accommodated in the second sliding groove and can move back and forth between two opposite inner side surfaces of the second sliding groove; the pressing plate is located above the second sliding piece and connected to the second sliding piece and the second base.
Preferably, the second sliding seat assembly further comprises an adjusting rod penetrating at least one side of the second base corresponding to the moving direction of the second sliding piece; one end of the adjusting rod penetrates into the second sliding groove to abut against or be away from the second sliding piece.
Preferably, the first slide assembly is provided in plurality and is distributed at least on the outer side surface of the pressure vessel of the reactor equipment, the outer side surface of the steam generator and the outer side surface of the main pump; the first sliding seat assembly arranged on the outer side surface of the steam generator is positioned on the central connecting line of the pressure container and the steam generator; the first sliding seat assembly arranged on the outer side surface of the main pump is positioned on the central connecting line of the pressure container and the main pump;
The second slide assembly is provided with a plurality of second slide assemblies which are at least distributed on the outer side face of the steam generator of the reactor equipment and are positioned on at least one side of the central connecting line of the pressure vessel and the steam generator.
Preferably, the horizontal support assembly comprises a damper, a support plate and a horizontal strut; one end of the damper is rotatably connected to the outer side surface of the upper part of the reactor equipment, the supporting plate is rotatably connected to the other end of the damper, and the horizontal supporting rod is arranged on the surface of the supporting plate, which is opposite to the damper, and is connected with the wall surface of the suppression box body.
Preferably, the horizontal support assembly further comprises a support lug fixed on the outer side surface of the upper part of the reactor equipment, and one end of the damper is rotatably connected to the support lug through a connecting lug and a rotating shaft.
The invention has the beneficial effects that: the horizontal supporting component, the sliding seat component and the supporting foundation are arranged in an upper-middle-lower three-layer module way, wherein the supporting reactor-loop equipment is installed and supported through the supporting foundation, and static load generated by the equipment and accessories thereof is transferred to the bottom of the reactor compartment; releasing thermal displacement of equipment generated when a cold state and a hot state of a reactor-loop system change through a sliding seat assembly arranged on a supporting base; the horizontal support component is arranged at the upper part of the reactor equipment, so that the stable state of the equipment is maintained under the working conditions of periodic alternating load, earthquake or horizontal impact load such as accident in the ocean environment, the horizontal displacement of the upper part of the equipment is limited, the bending moment and stress borne by the support at the lower part of the equipment are reduced, and the risk of equipment tipping is reduced, thereby improving the safety and reliability of the reactor-loop equipment in the ocean load environment.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic view of the reactor layered support apparatus of an embodiment of the present invention in a suppression tank;
FIG. 2 is a top view of the structure shown in FIG. 1;
FIG. 3 is a schematic view of a reactor layered support apparatus according to an embodiment of the present invention;
FIG. 4 is a bottom view of FIG. 3;
FIG. 5 is a schematic view of the first and second anti-sloshing separating assemblies of FIG. 3;
FIG. 6 is a schematic view of the structure of a first carriage assembly in a reactor layered support apparatus according to an embodiment of the present invention;
FIG. 7 is a schematic view of a second carriage assembly in a reactor layered support apparatus according to an embodiment of the present invention;
Fig. 8 is a schematic view of the structure of a horizontal support assembly in a reactor layered support apparatus according to an embodiment of the present invention.
Detailed Description
For a clearer understanding of technical features, objects and effects of the present invention, a detailed description of embodiments of the present invention will be made with reference to the accompanying drawings.
The reactor layered support apparatus of the present invention is suitable for small-sized offshore reactors, and is provided in a reactor compartment for supporting reactor equipment (a loop equipment).
As shown in fig. 1 to 3, the reactor layered support apparatus of an embodiment of the present invention includes a support base 2 provided in a suppression tank 1 of a reactor compartment and supported below a reactor apparatus, first and second carriage assemblies 3 and 4 for releasing thermal displacement when the reactor apparatus changes cold and hot, and a horizontal support assembly 5 for restricting horizontal displacement of an upper portion of the reactor apparatus. The supporting foundation 2 is arranged in the repression water tank 1 and has a certain height, and is used for installing and supporting reactor equipment above the supporting foundation to form a lower layer module of the reactor layered supporting device. The first sliding seat assembly 3 is arranged on the supporting foundation 2 and matched with the outer side surface of the lower part of the reactor equipment, can radially release the self-expansion of the reactor equipment, realizes centering of the reactor equipment and provides lateral support. The second carriage assembly 4 is arranged on the support foundation 2 and cooperates with the outer lateral surface of the lower part of the reactor installation, mainly taking up the vertical load, forming a middle module of the reactor layered support with the first carriage assembly 3. One end of the horizontal supporting component 5 is rotatably connected to the outer side surface of the upper part of the reactor equipment, and the other end of the horizontal supporting component is fixedly connected to the inner wall surface of the repressing water tank 1 to form an upper layer module of the reactor layered supporting device, so that the equipment can be kept in a stable state under the working conditions of periodic alternating load, earthquake or horizontal impact load such as accident in the marine environment, the horizontal displacement of the upper part of the equipment is limited, the bending moment and stress borne by the lower part of the equipment are reduced, and the risk of equipment tipping is reduced.
As shown in fig. 3 and 4, the support foundation 2 may include a support cylinder assembly 10 for supporting a reactor apparatus, a support panel 20, a first anti-sloshing partition assembly 30, and a lateral support assembly 40.
Wherein the support cylinder assembly 10 is fixed on the bottom surface of the suppression tank 1, and the support panel 20 is arranged in parallel with the bottom surface of the suppression tank 1 on top of the support cylinder assembly 10 for mounting the reactor equipment. Inside the holding down tank 1, below the support panel 20 is an internal pond water environment in which the entire support cartridge assembly 10 is immersed. The first anti-sloshing separating assembly 30 is provided at opposite sides of the support cylinder assembly 10 and connected between the support panel 20 and the bottom surface of the holding tank 1, and serves to separate a space while also transmitting a load of equipment to the bottom surface of the holding tank 1. The transverse supporting component 40 is connected between the supporting cylinder component 10 and the inner wall surface of the repressing water tank 1, so that the rigidity of the whole device is enhanced, and transverse load generated under the marine environment working condition can be transferred to the inner wall of the repressing water tank 1 and then to the wall surface of the reactor bulkhead, thereby providing a stable and reliable supporting foundation for loop equipment.
Typically, the reactor apparatus includes a pressure vessel, a steam generator, a main pump, and the like. In this embodiment, there are two steam generators 7 respectively provided on opposite sides of the pressure vessel 6 and connected to the pressure vessel 6, and a main pump 8 is provided on at least one side of the pressure vessel 6 and connected to the pressure vessel 6. Correspondingly, the support cylinder assembly 10 comprises a first support cylinder 11 supporting the pressure vessel 6, two second support cylinders 12 for supporting the steam generator 7, the two second support cylinders 12 being oppositely arranged on opposite sides of the first support cylinder 11.
Referring to fig. 2 to 4, the repressurization water tank 1 has a quadrangular structure, and a first support cylinder 11 and a second support cylinder 12 are arranged on a diagonal line of the repressurization water tank 1. Specifically, the first support cylinder 11 is at the center of the holding tank 1, and two second support cylinders 12 are arranged on opposite sides of the first support cylinder 12 along a diagonal line.
The first support cylinder 11 and the second support cylinder 12 have a cylindrical structure.
The supporting cylinder assembly 10 further comprises a reinforcing rib assembly 14 arranged on the outer side surface of the first supporting cylinder 11 and/or the second supporting cylinder 12, so that the rigidity of the first supporting cylinder 11 and/or the second supporting cylinder 12 is improved, the influence of film stress and bending stress on the surface of the supporting cylinder assembly is effectively reduced, and the supporting cylinder assembly can bear impact loads such as larger sea wave impact and external impact.
The stiffener assembly 14 may include at least one stiffener ring 141 and at least one stiffener 141. The reinforcing ring 141 is provided on the outer side surface of the first support cylinder 11 and/or the second support cylinder 12, and the reinforcing rib 142 is provided on the outer side surface of the first support cylinder 11 and/or the second support cylinder 12. Depending on the location of the reinforcing rib 142 on the outer side, it can be connected at least one position between the reinforcing ring 141 and the support panel 20, between the reinforcing ring 141 and the bottom surface of the suppression tank 1 and between adjacent reinforcing rings 141.
The support cylinder assembly 10 further includes at least one coupling web 15; the coupling rib 15 is connected between the first support cylinder 11 and the stiffener assembly 14 on the second support cylinder 12. In this embodiment, the outer side surfaces of the first supporting cylinder 11 and the second supporting cylinder 12 are respectively provided with a reinforcing rib assembly 14, and a connecting rib plate 15 is connected between the reinforcing rib assembly 14 of each second supporting cylinder 12 and the reinforcing rib assembly 14 of the first supporting cylinder 11. Both ends of the coupling rib 15 are welded to the reinforcing rings 141, respectively.
The connecting rib plates 15 connect the first supporting cylinder 11 and the second supporting cylinder 12 into a whole, so that the structural rigidity of the supporting cylinder assembly 10 is improved, and fatigue failure caused by long-term ocean periodic alternating load of the supporting cylinder assembly 10 in the service life period is avoided.
The support panel 20 is secured to the top of the support cylinder assembly 10 by welding or the like to provide a support surface for the apparatus. The support panel 20 has an outer peripheral dimension that is larger than the corresponding dimension of the outer periphery of the support cylinder assembly 10, and may be, for example, diamond-shaped as shown in fig. 4.
The first anti-sloshing separating assembly 30 is provided on the other opposite sides of the first supporting cylinder 11, differently from the two second supporting cylinders 12. In the holding tank 1, the first anti-sloshing separating assembly 20 is located on another diagonal of the holding tank 1, but may also be slightly off the diagonal. Alternatively, the first anti-sloshing separating assembly 30 may include at least two first anti-sloshing partitions 31, at least one first anti-sloshing partition 31 being provided at each of opposite sides of the first supporting cylinder 11, thereby partitioning the space at each side of the first supporting cylinder 11 into at least two spaces, reducing impact load of the pool water to the supporting cylinder assembly 10, etc.
Referring to fig. 4 and 5, in the present embodiment, two first anti-sloshing partitions 31 are provided on each of opposite sides of the first supporting cylinder 11. The two first shaking prevention baffles 31 are opposite to each other at intervals, one side of the first shaking prevention baffles is fixed on the outer side surface of the first supporting cylinder 11 by welding or the like, the other side of the first shaking prevention baffles faces the inner wall surface of the pressure-restraining water tank 1, and the top and the bottom of the first shaking prevention baffles are respectively fixed on the supporting panel 20 and the bottom surface of the pressure-restraining water tank 1.
In addition, the first anti-sloshing partition plate 31 may further be provided with a first water through hole 32 for the pool water in the pressure-inhibiting water tank 1 to pass through, so as to prevent a large internal impact load generated by sloshing of the pool water.
The lateral support assembly 40 may include a plurality of lateral support columns 41 spaced along the periphery of the support cylinder assembly 10, parallel to the bottom surface of the suppression cistern 1, connected at one end to the support cylinder assembly 10 and at the other end to the inner wall surface of the suppression cistern 1.
Specifically, the plurality of lateral support columns 41 are distributed corresponding to the arrangement positions of the first support cylinder 11 and the second support cylinder 12. One end of the corresponding supporting cylinder assembly 10 is connected to the outer side surface of the first supporting cylinder 11 or the second supporting cylinder 12, the reinforcing rib assembly 14 of the first supporting cylinder 11 or the second supporting cylinder 12 or the connecting rib plate 15. In this embodiment, the cross section of the transverse supporting column 41 is T-shaped, and may be formed by welding steel plates, and one end of the transverse supporting column, which corresponds to the inner wall of the pressure-suppressing water tank 1, is welded to the inner wall surface of the pressure-suppressing water tank 1 through a backing plate 42.
Further, the support base 2 further includes a second anti-sloshing separating assembly 50 connected between the first support cylinder 11 and the second support cylinder 12, enhancing stability between the first support cylinder 11 and the second support cylinder 12.
The second anti-sloshing separating assembly 50 may include at least two second anti-sloshing partitions 51; each second support cylinder 12 is connected to the first support cylinder 11 with at least one second anti-sloshing baffle 51. The second anti-sloshing baffle 51 is also located on a diagonal of the repressurization water tank 1 corresponding to the arrangement of the second support cylinder 12 and the first support cylinder 11.
As shown in fig. 5, the second anti-sloshing baffle 51 and the first anti-sloshing baffle 31 are perpendicular to each other in the pressure-suppressing tank 1. The second shaking prevention partition plate 51 may further be provided with a second water through hole 52 for passing the pool water, thereby preventing an impact load generated by shaking of the pool water.
Further, the support foundation 2 also comprises a plurality of longitudinal support columns 60. A plurality of longitudinal support columns 60 are provided outside the support cylinder assembly 10 and/or the first anti-sloshing partition assembly 30, are vertically connected between the support panel 20 and the bottom surface of the holding tank 1, and promote the structural rigidity of the entire support foundation 2, provide support points for a loop apparatus, and transfer weight to the bottom surface of the holding tank 1.
In this embodiment, as shown in fig. 3 and 4, a plurality of spaced apart longitudinal support columns 60 are provided on the outer side surfaces of the first support cylinder 11 and the second support cylinder 12, respectively. Depending on the location where the longitudinal support columns 60 are arranged, the longitudinal support columns 60 may also be connected to adjacent stiffener assemblies 14, second stiffener assemblies 16 or coupling webs 15 to achieve integration of the support foundation 2. The first anti-sloshing partition assembly 30 is also provided with a longitudinal support column 60, and the longitudinal support column 60 is attached to the first anti-sloshing partition plate 31 on the side facing the inner wall surface of the pressure-suppressing tank 1.
Preferably, the longitudinal support post 60 is H-shaped in cross section and is integrally splice welded from sheet steel.
As shown in fig. 1-3 and 6, the first carriage assembly 3 may include a first carriage mechanism 301 and a first slider 302. The first slider mechanism 301 is fixed to the support base 2 by a fastener such as a bolt. The first slider 302 is provided on the first carriage mechanism 301, and is movable back and forth in the radial direction of the reactor apparatus with respect to the first carriage mechanism 301. One end of the first sliding member 302 is connected to the outer side surface of the reactor equipment, and when the reactor equipment self-expands, the first sliding member 302 is driven to move relative to the first sliding seat mechanism 301 in a direction away from the reactor equipment in a radial direction. The first sliding member 302 may have a block structure, and an end surface connected to the reactor apparatus may be configured to match the shape of the outer side of the apparatus, for example, an arc shape; of course, it can also be planar and fit on the outside of the device by welding.
The first sliding mechanism 301 may include a first base 311 and a cover 312. The first base 311 may be formed by connecting a plurality of members, or may be a unitary structure; the first base 311 is provided with a first sliding groove 313, and the first sliding groove 313 penetrates through two opposite sides of the first base 311, and the cross section shape of the first sliding groove is matched with the shape of the first sliding piece 302. The first slider 302 is accommodated in the first sliding groove 313 and can move back and forth along the first sliding groove 303 in the directions of two opposite sides of the first base 311. The cover plate 312 may be coupled to the first base 311 by a fastener, closing the top opening of the first sliding groove 313.
As shown in fig. 1-3 and 7, the second carriage assembly 4 may include a second carriage mechanism 401 and a second slider 402. The second carriage mechanism 401 is fixed to the support base 2 by a fastener such as a bolt. A second slider 402 is provided on the second carriage mechanism 401, with one end connected to the outer side of the reactor apparatus. The second slider 402 is movable back and forth in a linear direction between parallel reactor units with respect to the second carriage mechanism 401, enabling a limited multidirectional displacement of the reactor units.
The second carriage mechanism 401 may include a second base 411 and a platen 412. The second base 411 may be formed by connecting a plurality of members, or may be a unitary structure; the second base 411 is provided with a second sliding groove 413, and the second sliding piece 402 is accommodated in the second sliding groove 413 and can move back and forth between two opposite inner side surfaces of the second sliding groove 413; a platen 412 is coupled to the second slider 402 and the second base 411 above the second slider 402. Specifically, the pressing plate 412 has one end connected to the second base 411 through a connection shaft and the other end connected to the second slider 402 through a connection shaft, thereby allowing the second slider 402 to move relative to the second base 411. The second slider 402 may have a block structure, and the end surface of the reactor apparatus may be configured to match the shape of the outer side of the apparatus, for example, may be arc-shaped; of course, it can also be planar and fit on the outside of the device by welding.
In addition, the second slider assembly 4 further includes an adjustment rod 403 penetrating at least one side of the second base 411 corresponding to the moving direction of the second slider 402. One end of the adjustment lever 403 penetrates into the second sliding groove 413 to abut against or be away from the second slider 402. The length of one end of the adjusting rod 403 penetrating into the second sliding groove 413 is adjustable, and the width of the second sliding groove 413 for the movement of the second sliding piece 402 can be adjusted by adjusting the length, and the second sliding piece 402 can be positioned by abutting against the side surface of the second sliding piece 402.
As shown in fig. 1 and 2, in the present embodiment, the first carriage assembly 3 is provided in plurality, at least on the outer side of the lower portion of the pressure vessel 6, the outer side of the lower portion of the steam generator 7, and the outer side of the lower portion of the main pump 8. In particular, the plurality of first slide assemblies 3 on the lower outer side of the pressure vessel 6 are preferably symmetrically arranged and can be distributed between the pressure vessel 6 and the connecting pipes of the steam generator 7 and the main pump 8. The first sliding seat component 3 arranged on the outer side surface of the lower part of the steam generator 7 is positioned on the central connecting line of the pressure container 6 and the steam generator 7, and the first sliding seat component 3 is positioned on the opposite sides of the two steam generators 6; the first slide assembly 3 arranged on the outer side of the lower part of the main pump 8 is arranged on the central connecting line of the pressure vessel 6 and the main pump 8, and the first slide assembly 3 is arranged on the side of the main pump 8 facing away from the pressure vessel 6.
During the cold-hot state change of the reactor, when the pressure vessel 6 is heated and expands, the first sliding piece 302 of the first sliding seat assembly 3 can move relative to the first sliding seat mechanism 301 in the radial direction of the pressure vessel 6, so as to release the self-expansion of the pressure vessel 6, realize the centering of the pressure vessel 6 and provide lateral support. With the self-expansion of the pressure vessel 6, the steam generator 7 and the main pump 8 are driven by the connecting pipe to slightly move along the central connecting line, so that the first sliding piece 302 on the first sliding seat assembly 3 outside the steam generator 7 and the main pump 8 also radially moves.
The second carriage assembly 4 is provided in plurality at least on the outer side of the lower part of the steam generator 7 and on at least one side of the central line connecting the pressure vessel 6 and the steam generator 7. During the cold-hot state change process of the reactor, when the pressure vessel 6 is heated and expanded, the connecting pipeline and the steam generator 7 are driven to move along the central connecting line of the pressure vessel 6 and the steam generator 7, so that the second sliding piece 402 of the second sliding seat assembly 4 can be driven to move in the second sliding groove 413 along the central connecting line relative to the second sliding seat mechanism 401, and the limited multi-directional displacement of the steam generator 7 is realized.
The reactor layered support arrangement of the invention further comprises a sledge platform 9 arranged on the top surface of the support foundation 2. The first carriage assembly 3 and the second carriage assembly 4 are each mounted to the support base 2 by a carriage platform 9, wherein the first carriage mechanism 301 and the second carriage mechanism 401 are secured to the carriage platform 9 by fasteners such as bolt assemblies.
In this embodiment, the carriage platform 9 includes a first annular or semi-annular platform 91 disposed at the periphery of the steam generator 7 and extending to the pressure vessel 6, and a second platform 92 distributed at the periphery of the main pump 8, the first platform 91 being for mounting thereon the first carriage assembly 3 on the outer side of the pressure vessel 6, the first carriage assembly 3 and the second carriage assembly 4 on the outer side of the steam generator 7, and the second platform 92 being for mounting thereon the first carriage assembly 4 on the outer side of the main pump 8. The areas of the first platform 91 and the second platform 92 are not required to be excessively large, and only the first sliding seat assembly 3 and the second sliding seat assembly 4 are required to be installed, the top surface of the whole supporting foundation 2 is not required to be covered, so that a space is reserved for installing, operating and maintaining other components such as equipment accessories and the like.
As shown in fig. 8, the horizontal support assembly 5 may include a damper 501, a support plate 502, and a horizontal strut 503. One end of the damper 501 is rotatably connected to the outer side surface of the upper part of the reactor equipment, the other end of the damper is rotatably connected with the supporting plate 502, the horizontal supporting rod 503 is arranged on the surface of the supporting plate 503 facing away from the damper 501 and is connected with the wall surface of the repression water tank 1, so that the horizontal supporting component 5 is supported and connected between the upper part of the reactor equipment and the wall surface of the repression water tank 1, and the horizontal movement of the upper part of the reactor equipment is limited when the upper part of the reactor equipment shakes under some horizontal impact load conditions.
The damper 501 may be forced to stretch and the opposite ends may be relatively stretched or contracted. The opposite ends of the damper 501 are provided with coupling lugs 511, 512, respectively, for mating connection with the reactor apparatus and the support plate 502. The surface of the supporting plate 502 facing the damper 501 is provided with a convex connecting part 505, and one end of the damper 51 is rotatably connected with the connecting part 505 through a connecting lug 512 and a rotating shaft 514.
The directional horizontal support assembly 5 further includes a support lug 504 fixed to the outer side surface of the upper portion of the reactor apparatus, and one end of the damper 501 is rotatably coupled to the support lug 504 through a coupling lug 511 and a rotation shaft 513.
In addition, the connection lugs 511 and 512 connect the reactor equipment and the support plate 502, and the end surfaces at both ends are cambered surfaces, so that friction is reduced.
The horizontal struts 503 may be provided in plurality, vertically and uniformly arranged on the surface of the supporting plate 502.
Referring to fig. 1 to 3, in the present embodiment, the horizontal support assembly 5 is mainly provided on the upper outer side surfaces of the steam generator 7 and the main pump 8. At least one horizontal support assembly 5 is provided at the upper part of the steam generator 7 and at the upper part of the main pump 8, respectively. In particular, the upper outer side of the steam generator 7 is provided with two horizontal support assemblies 5, the two horizontal support assemblies 5 being on the side of the steam generator 7 facing away from the pressure vessel 1, and preferably at the same level. The upper outer side of the main pump 8 is also provided with two horizontal support assemblies 5, the two horizontal support assemblies 5 being on the side of the main pump 8 facing away from the pressure vessel 1, and preferably at the same level.
The reactor layered support device of the invention is compact and reasonable in overall arrangement. In use, the pressure vessel 6, the steam generator 7, the main pump 8, etc. of the one-circuit device are mounted on the support panel 20 at corresponding positions, and the first slide assembly 3 and the second slide assembly 4 are mounted between the outer side surfaces of the required devices in the pressure vessel 6, the steam generator 7, the main pump 8, and the slide platform 9. Under the marine environment working condition, the supporting device transmits the environmental load (including inertial load caused by rolling, pitching, heave and the like, impact load of sea waves and the like) and static load generated by weight of loop equipment, equipment accessories, pipelines and the like to the bottom surface and the wall surface of the pressure-restraining water tank 1 through the supporting foundation 2, so that the possibility of impact damage to each structural member is reduced, the first sliding seat assembly 3 and the second sliding seat assembly 4 release thermal displacement of the equipment when the cold state and the hot state of the loop system of the reactor change, the horizontal supporting assembly 5 enables the equipment to maintain a stable state under the marine environment periodic alternating load, earthquake or accident and other horizontal impact load working conditions, bending moment and stress borne by the lower supporting part of the equipment are reduced, and the risk of equipment overturning is reduced, thereby improving the safety and reliability of the loop equipment of the reactor in the marine environment.
The foregoing description is only illustrative of the present invention and is not intended to limit the scope of the invention, and all equivalent structures or equivalent processes or direct or indirect application in other related technical fields are included in the scope of the present invention.
Claims (15)
1. A reactor layered support device, characterized by comprising a support foundation (2) arranged in a repression water tank (1) of a reactor compartment and supported below a reactor apparatus, a first slide assembly (3) and a second slide assembly (4) for releasing thermal displacement when the reactor apparatus changes cold and heat, and a horizontal support assembly (5) for limiting horizontal displacement of the upper part of the reactor apparatus;
The first sliding seat assembly (3) and the second sliding seat assembly (4) are arranged on the supporting foundation (2) and are connected with the outer side surface of the lower part of the reactor equipment; one end of the horizontal supporting component (5) is rotatably connected to the outer side surface of the upper part of the reactor equipment, and the other end of the horizontal supporting component is fixedly connected to the inner wall surface of the pressure-inhibiting water tank (1);
the supporting foundation (2) comprises a supporting cylinder assembly (10) fixed on the bottom surface of the pressure-restraining water tank (1), a supporting panel (20) parallel to the bottom surface of the pressure-restraining water tank (1) and arranged at the top of the supporting cylinder assembly (10), first anti-shaking separation assemblies (30) arranged on two opposite sides of the supporting cylinder assembly (10) and connected between the supporting panel (20) and the bottom surface of the pressure-restraining water tank (1), and a transverse supporting assembly (40) connected between the supporting cylinder assembly (10) and the inner wall surface of the pressure-restraining water tank (1);
the first slide carriage assembly (3) and the second slide carriage assembly (4) are arranged on the support panel (20);
The support cylinder assembly (10) comprises a first support cylinder (11) for supporting a pressure vessel (6) of a reactor apparatus, two second support cylinders (12) for supporting a steam generator (7) of the reactor apparatus, the two second support cylinders (12) being oppositely arranged on opposite sides of the first support cylinder (11);
the first anti-sloshing separating assemblies (30) are disposed on the other opposite sides of the first supporting cylinder (11).
2. Reactor layered support arrangement according to claim 1, characterized in that the first anti-sloshing separation assembly (30) comprises at least two first anti-sloshing partitions (31), at least one first anti-sloshing partition (31) being provided on each of opposite sides of the first support cylinder (11);
the first shaking prevention baffle plate (31) is provided with a first water through hole (32).
3. Reactor layered support arrangement according to claim 1, characterized in that the support foundation (2) further comprises a second anti-sloshing separation assembly (50); the second anti-sloshing separation assembly (50) is connected between the first support cylinder (11) and the second support cylinder (12).
4. A reactor layered support arrangement according to claim 3, characterized in that the second anti-sloshing separation assembly (50) comprises at least two second anti-sloshing partitions (51); -each of said second support cylinders (12) is connected to said first support cylinder (11) with at least one of said second anti-shake spacers (51);
the second shaking prevention baffle plate (51) is provided with a second water through hole (52).
5. The reactor layered support arrangement according to claim 1, characterized in that the support cylinder assembly (10) further comprises a stiffener assembly (14) arranged on the outer side of the first support cylinder (11) and/or the second support cylinder (12).
6. The reactor layered support arrangement according to claim 5, characterized in that the support cylinder assembly (10) further comprises at least one coupling web (15); the connecting rib plate (15) is connected between the first supporting cylinder (11) and the reinforcing rib assembly (14) on the second supporting cylinder (12).
7. The reactor layered support arrangement according to claim 1, characterized in that the support foundation (2) further comprises a plurality of longitudinal support columns (60);
a plurality of longitudinal supporting columns (60) are arranged outside the supporting cylinder assembly (10) and/or the first anti-shaking separation assembly (30), and are vertically connected between the supporting panel (20) and the bottom surface of the pressure-restraining water tank (1).
8. The reactor layered support arrangement according to any of the claims 1-7, characterized in that the first slide assembly (3) comprises a first slide mechanism (301) fixed to the support foundation (2), a first slide (302) arranged on the first slide mechanism (301), one end of the first slide (302) being connected to the outer side of the lower part of the reactor arrangement, being movable back and forth in the radial direction of the reactor arrangement with respect to the first slide mechanism (301);
The second sliding seat assembly (4) comprises a second sliding seat mechanism (401) fixed on the supporting base (2), and a second sliding piece (402) arranged on the second sliding seat mechanism (401), wherein one end of the second sliding piece (402) is connected to the outer side surface of the lower part of the reactor equipment, and can move back and forth in the connecting line direction between parallel reactor equipment relative to the second sliding seat mechanism (401).
9. Reactor layered support according to claim 8, characterized in that it further comprises a sliding platform (9) provided on the top surface of the support foundation (2); the first (301) and second (401) slide mechanisms are fixed to the slide platform (9).
10. The reactor layered support arrangement according to claim 8, wherein the first slide mechanism (301) comprises a first base (311) and a cover plate (312), wherein the first base (311) is provided with a first sliding groove (313), the first sliding groove (313) penetrates through two opposite sides of the first base (311), and the first sliding piece (302) is accommodated in the first sliding groove (313) and can move back and forth in the directions of two opposite sides of the first base (311); the cover plate (312) is connected to the first base (311) and closes the top opening of the first sliding groove (313).
11. The reactor layered support arrangement according to claim 8, wherein the second carriage mechanism (401) comprises a second base (411) and a platen (412), the second base (411) being provided with a second sliding groove (413), the second sliding member (402) being accommodated in the second sliding groove (413) and being movable back and forth between opposite inner sides of the second sliding groove (413); the pressing plate (412) is positioned above the second sliding piece (402) and connected to the second sliding piece (402) and the second base (411).
12. The reactor layered support arrangement according to claim 11, characterized in that the second carriage assembly (4) further comprises an adjustment rod (403) threaded on at least one side of the second base (411) in correspondence of the direction of movement of the second slider (402); one end of the adjusting rod (403) penetrates into the second sliding groove (413) to abut against or be far away from the second sliding piece (402).
13. Reactor layered support according to any of claims 1-7, characterized in that the first carriage assembly (3) is provided in plurality, at least distributed on the outer side of the pressure vessel (6) of the reactor plant, on the outer side of the steam generator (7) and on the outer side of the main pump (8); the first sliding seat assembly (3) arranged on the outer side surface of the steam generator (7) is positioned on the central connecting line of the pressure container (6) and the steam generator (7); the first sliding seat assembly (3) arranged on the outer side surface of the main pump (8) is positioned on the central connecting line of the pressure container (6) and the main pump (8);
the second slide assembly (4) is provided with a plurality of second slide assemblies which are at least distributed on the outer side surface of the steam generator (7) of the reactor equipment and are positioned on at least one side of the central connecting line of the pressure vessel (6) and the steam generator (7).
14. The reactor layered support arrangement according to any one of claims 1-7, wherein the horizontal support assembly (5) comprises a damper (501), a support plate (502) and a horizontal strut (503); one end of the damper (501) is rotatably connected to the outer side surface of the upper part of the reactor equipment, the supporting plate (502) is rotatably connected to the other end of the damper (501), and the horizontal supporting rod (503) is arranged on the surface of the supporting plate (502) facing away from the damper (501) and is connected with the wall surface of the repressing water tank (1).
15. The reactor layered support arrangement according to claim 14, characterized in that the horizontal support assembly (5) further comprises a support lug (504) fixed to the upper outer side of the reactor apparatus, one end of the damper (501) being rotatably connected to the support lug (504) by means of a connecting lug (511) and a rotating shaft (513).
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| CN201810866817.5A CN108953855B (en) | 2018-08-01 | 2018-08-01 | Layered support device for reactor |
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| CN201810866817.5A CN108953855B (en) | 2018-08-01 | 2018-08-01 | Layered support device for reactor |
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| CN108953855B true CN108953855B (en) | 2024-06-18 |
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Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4115194A (en) * | 1977-02-22 | 1978-09-19 | The Babcock & Wilcox Company | Reactor pressure vessel support |
| US4786462A (en) * | 1984-02-21 | 1988-11-22 | Stone & Webster Engineering Corp. | Support structure for a nuclear reactor |
| CN208982893U (en) * | 2018-08-01 | 2019-06-14 | 中广核研究院有限公司 | Reactor is layered supporting arrangement |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11125685A (en) * | 1997-10-22 | 1999-05-11 | Babcock Hitachi Kk | Support device of reactor pressure vessel |
| CA2535280C (en) * | 2003-08-15 | 2013-02-19 | Pebble Bed Modular Reactor (Proprietary) Limited | A support arrangement |
| CN1312701C (en) * | 2005-01-07 | 2007-04-25 | 清华大学 | Damper-free support system for modular high temperature air-cooled pile pressure casing |
| CN102798115B (en) * | 2012-08-17 | 2016-01-27 | 中广核工程有限公司 | A kind of nuclear power station steam generator supporting structure and steam generator |
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2018
- 2018-08-01 CN CN201810866817.5A patent/CN108953855B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4115194A (en) * | 1977-02-22 | 1978-09-19 | The Babcock & Wilcox Company | Reactor pressure vessel support |
| US4786462A (en) * | 1984-02-21 | 1988-11-22 | Stone & Webster Engineering Corp. | Support structure for a nuclear reactor |
| CN208982893U (en) * | 2018-08-01 | 2019-06-14 | 中广核研究院有限公司 | Reactor is layered supporting arrangement |
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